DCL-04-002, Inservice Testing (IST) Program Plan, Revision 20

Inservice Testing (IST) Program Plan, Revision 20

ML040140195
Person / Time
Site:	Diablo Canyon
Issue date:	01/09/2004
From:	Becker J Pacific Gas & Electric Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
DCL-04-002
Download: ML040140195 (136)

Text

lW Pacific Gas and lecac Company James R.Becker Diablo Canyon Power Plant Vice President-Diablo Canyon PO. Box 56 Operations and Station Director Avila Beach, CA 93424 January 9, 2004 805.545.3462 Fax: 805.545.4234 PG&E Letter No. DCL-04-002 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Docket No. 50-275, OL-DPR-80 Docket No. 50-323, OL-DPR-82 Diablo Canyon Units 1 and 2 Inservice Testing (1ST) Proaram Plan. Revision 20

Dear Commissioners and Staff:

Enclosed for your information is the Diablo Canyon Power Plant, Units 1 and 2, IST Program Plan, Revision 20, effective December 9, 2003. Submittal of the ST Program Plan is recommended in accordance with the guidance provided in NUREG-1482, Guidelines for Inservice Testing at Nuclear Power Plants," Question Group 61.

Revision 20 of the IST Program Plan incorporates editorial corrections and updates.

A summary of the changes is provided and revision bars in the enclosure identify the specific change locations in the IST Program Plan.

Sincerely, James R. ecker ddm/469 Enclosure cc: Bruce S. Malleft, Region IV David L. Prouix, Senior Resident Inspector Diablo Distribution cclenc: Girija S. Shukla, NRR State of Califomia, Pressure Vessel Unit A member of the STARS (Strategic Teaming and Resource Sharing) Alliance Callaway

• Comanche Peak

• Diablo Canyon

• Palo Verde

• South Texas Project

• Wolf Creek

Enclosure PG&E Letter DCL-04-002 REVISION 20 INSERVICE TESTING PROGRAM SECOND TEN-YEAR INTERVAL DIABLO CANYON POWER PLANT

12/09/03 DIABLO CANYON POWER PLANT IST PROGRAM PLAN Rev. 20 DISTRIBUTION COPY NO. COPY HOLDER DEPARTMENT LOCATION 1 Lynn Walter Engineering Services 104/4 2,5,7,13, Deleted 14,15 & 17 3 Kenny Kim IST/ANII 104/3 4 Paul Provence Library 104/4/DS 6 Stan Ketelsen Regulatory Compliance 104/5/536 (Plus 2 Controlled Copies) 8 Jeff Hodges NQS 104/3/23B 9 Robert Savard Engineering Services 104/4/9B 10 NRC Resident NRC 104/5/543 11 John Hjalmarson IST Coordinator 104/3/37A 12 Don Shelley ECCS System Engineering 104/4 16 Control Room DCPP Operations Control Room 18 McCoy Burgess Component Engineering 104/3/35A 19 Ed Chaloupka Surveillance Engineering 104/4/48B

Page 1 of 2

SUMMARY

OF CHANGES TO THE IST PROGRAM PLAN REVISION 20 SECOND TEN-YEAR INTERVAL Listed below are the significant changes to the IST Program Plan revision 20 A. Introduction There were no changes made to the Introduction section.

B. Pumps There were no changes made to the Pumps section.

C. Pumps Relief Requests There were no changes made to the Pumps Relief Requests section.

D. Valves

1. On page 24 of 52 changed procedure number for the partial stroke test of check valve 8820 from STP V-4A to ST? V-4B.

2. On page 30 of 52 changed procedure number for the leak test of motor operated valve RHR-8703 from STP V-7D to STP V-5C.

3. On page 31 of 52 changed procedure number for the full stroke test of check valves RHR-8730A, -8730B, -8742A and -8742B from ST? V-4A to ST? V-4B.

4. On page 31 of 52 deleted disassembly and mechanical exercise of check valves RHR-2-8740A, and -8740B. S V-18C has been revised with improved flow test and non intrusive test method, thus eliminating need for disassembly.

5. On page 35 of 52 deleted disassembly and mechanical exercise of check valves CS-9002A, and -9002B. New test procedure STP V-17 was used during 2R I to obtain Non Intrusive Test Data, thus eliminating need for disassembly.

Page 2 of 2 E. Cold Shutdown Justification Statements There were no changes made to the Cold Shutdown Justifications section.

F. Refueling Outage Justification Statements

1. NO. V-ROIO. Deleted last sentence in Basis section. This sentence stated that the ASW vacuum breaker valves SW-34, -170, -301 and -303 will be disassembled and manually stroked every 6 months for maintenance reasons. AR A0589222 from system engineer requested this change.

2. NO. V-R012. Changed this refuelingjustification statement because check valves RHR-8740A&B test requirements are being changed to full stroke exercise using flow per STP V-1 SC. Previously the unit one valves were full stroke open tested using flow and NIT and the unit two valves were disassembled and inspected.

G. Valve Relief Requests

1. Changed summary pages I of 9 and 2 of 9. Deleted approval status lines for deleted relief requests #3 and #6. Changed approval status line for relief request #10 from pre approved per GL 89-04 to pre approved per NUREG 1482.

2. Deleted NO. V-RR7. This relief request pertained to unit two RHR-8740A&B because they were being disassembled on a rotational refueling outage frequency. Now they will be full stroke exercised with flow on a refueling outage frequency (see refueling justification statement V-RO 12.

3. Changed NO. V-RRIO for containment spray system check valves 9002A&B. The old relief request was to disassemble and inspect on an outage rotational frequency. The new relief request is to perform NIT on an outage rotational frequency.

REVISION 20 November 12, 2003 INSERVICE TESTING PROGRAM SECOND TEN-YEAR INTERVAL DIABLO CANYON POWER PLANT UNITS I AND 2 USNRC DOCKET NOS. 50-275/50-323 FACILITY OPERATING LICENSE NOS. DPR-80/82 COMMERCIAL OPERATION DATES: MAY 7,1985/MARCH 13, 1986 Prepared by:

Jon Hjalmson STCodina 11/12/2003 Reviewed by:

Edward Chaloupka, Por PrdcinEngineer // IL2003 Approved: PSRC Date elkr Z/3)1 / /2003 Approved by: JimV- Statio k1 2Director P.,r 4 Jim Becker, Station Director I 2. //2003 10006620.1ST 40MIS I

REVISION 20 November 12. 2003 INSERVICE TESTING PROGRAM PLAN SECOND TEN-YEAR INTERVAL INTRODUCTION This volume describes the Inservice Testing (IST) Program Plan for Diablo Canyon Power Plant's safety-related components (pumps and valves) which are classified ASME Code Class 1,Class 2, and Class 3.

This IST Program Plan complies with the requirements of 10 CFR Part 50.55a(a), Part 50.55a(b) (2), and Part 50.55a(f), effective December 31, 1992, as follows:

10CFR50.55a(f) - For a pressurized water-cooled nuclear facilities (PWR) whose construction permit was issued prior to January 1, 1971 (Unit I's was issued April 23, 1968 and Unit 2's was issued December 9, 1970), pumps and valves must meet the requirements of paragraphs (f) (4) and (5).

10CFR50.55a(f) (4) - Throughout the service life of a PWR, ASME Code Class 1, 2, or3 pumps and valves must meet the IST requirements set forth in Section Xl of the ASME B&PV Code and Addenda that are incorporated by reference in paragraph (b) of this section, to the extent practical within the limitations of design, geometry and materials of construction of such components.

I OCFR50.55a(b) (2) - ... references to Section XI of the ASME B&PV Code refer to Section XI, Division 1,and include addenda through the 1988 Addenda and editions through the 1989 Edition.

IOCFR50.55a(f) (4) (ii) - Inservice tests conducted during successive 120month intervals must comply with the requirements of the latest edition and addenda of the Code incorporated by reference in paragraph (b) of this section 12 months prior to the start of the 120-month interval, subject to the limitations and modifications listed in paragraph (b).

IOCFRS0.5 aff) (4) (iv) - IST of pumps and valves may meet the requirements set forth in subsequent editions and addenda that are incorporated by reference in paragraph (b),

subject to the limitations and modifications listed in paragraph (b), and subject to Commission approval. Portions of editions or addenda may be used provided that all related requirement of the respective additions or addenda are met.

10CFR50.55a(f) (5) (i) - The IST program for a PWR must be revised, as necessary, to meet the requirements of paragraph (f) (4).

(I) 10006620.1ST 40MIS 2

REVISION 20 November 12, 2003 The 1989 Edition of the ASME Boiler and Pressure Vessel Code,Section XI, is no longer involved in testing of pumps and valves. This responsibility has been assumed by the ASME/ANSI Operations and K> Maintenance of Nuclear Power Plants Standard (OM).Section XI, Subsections WP (pumps) and JWV (valves), no longer contains requirements for pump and valve testing. Instead these subsections state that testing shall be performed in accordance with the requirements stated in ASME/ANSI OM (Part 6) (or(Part 10)). Table IWA-1600-1 of Subsection IWA of Section XI gives the specific revision dates for ASMEIANSI OM Parts 6 and 10 as 1987 including 1987A addenda. The 1987A addenda was later corrected to the OMa-1988 addenda. This is also stated in 10CFR50.55a(b) (2) (viii).

The initial testing interval for Unit I began May 7, 1985, and for Unit 2 began March 13, 1986, when the respective Units were placed into commercial operation.

The second ten-year interval began January 1, 1996 for Unit I and June 1, 1996 for Unit 2.

ASME Section XI, subsection IWA-2400, allows each IST interval to be decreased or extended by as much as one year (see also NRC NUREG-1482, section 3.3.1). This allowance has been applied as follows:

(a) Unit l's first ten-year IST interval has been increased by approximately 8 months.

(b) Unit 2's first ten-year IST interval has been increased by approximately 2.5 months.

K2 (2) '

10006620.1ST 40MIS 3

REVISION 20 November 12. 2003 Where conformance with certain Code requirements is impractical, requests for relief, in accordance with IOCFR5O.55a(a) (3) and IOCFR50.55a(f) (5), are included in each section with supporting information and

'%-' proposed alternatives. Preservice tests, where required, have been completed. All preservice test data is available for review at the plant site.

ASME SECTION XI CODE BOUNDARY DRAWINGS The ASME Code Classification Boundary Drawings, PG&E Number 102028 (Unit 1) and 104628 (Unit 2),

are located in Section 2.0 of the Inservice Inspection (ISI) Program Plan. Regulatory Guide 1.261 was used as the governing document in setting up the Inservice Inspection and Testing Program (ISIT) boundary. The drawings show the Code Class 1, 2, and 3 systems and components subject to inservice inspection and testing requirements. Systems and components are identified by Code Class and are color coded as applicable to indicate exemptions from various code requirements2 . These drawings are extracted from the piping schematics (P&ID's) for the plant that are contained in Section 3.2 of the FSAR. All ASME Code Class 1, 2, and 3 components subject to inservice testing are shown on the drawings. To emphasize the Section XI Code Boundaries, P&ID pages containing lines other than ASME Code Piping have been omitted and non-ASME lines have been ghosted on the pages included. An explanation of the color coding system is provided at the end of the drawings.

' Regulatory Guide 1.26, "Quality Classifications and Standards for Water-Stean, and Radioactive-Waste-Containing Components of Nuclear Power Plants.

2 As allowed by Paragraphs IWB-1220, IWC-1220, IWC-1230, and Table IWD-2500-1 of Section XI.

(3)

I0006620.1ST 40MIS 4

REVISION 20 November 12, 2003 INSERVICE TESTING OF PUMPS AND VALVES The pump and valve testing program demonstrates the operational readiness of Code Class 1,2, and 3 pumps and valves which are required to perform a specific function in shutting down the reactor to the cold shutdown condition or in mitigating the consequences of an accident. This program is presented in the attached Tables.

Table 1.0 (Pump IST Program) includes the pump name and number, the Code Class, applicable surveillance test procedure and test parameters, i.e., speed, differential pressure, discharge pressure, flow rate, pump bearings vibration, applicable relief request numbers, and remarks.

Table 1.1 contains all of the pump requests for relief from Code requirements.

Table 2.0 (Valve IST Program) includes the system name and number, valve number, description, P&ID coordinates, Code class, Code category, size, valve type (ball, butterfly, check, diaphragm, gate, globe, plug, or relief valve), actuator type (air operated, electric motor, electrohydraulic, manual, or solenoid-operated), normal valve position, test requirements, the test frequency, applicable stroke time and direction, relief request number (or cold shutdown or refueling outage justification numbers), procedure number, and remarks.

Table 2.1 contains all valve cold shutdown justifications per OMa-1988, Part 10, section 6.2(d).

Table 2.2 contains all valve refueling outage justifications per OMa-1988, Part 10, section 6.2(d).

Table 2.3 contains all of the valve requests for relief from Code requirements.

(4) 10006620.1ST 40MIS 5

REVISION 20 November 12. 2003 HOT STANDBY AS THE SAFE SHUTDOWN CONDITION NUREG-1482 Section 2.2 requires that the IST PP state the Safe Shutdown condition of the plant. Safe shutdown at Diablo Canyon Power Plant is defined as HOT STANDBY. DCPP SSER 7, page 3-3 and SSER 22, pages 93-95 indicate that DCPP is considered to be a Class 2 plant wherein a single suction line from RCS Hot Leg is considered acceptable since the plant has a safety related Auxiliary Feedwater system enabling decay heat removal for extended periods at Hot Standby. Technical Specification Bases B 3.3.4 states that "safe shutdown condition is defined as MODE 3. With the unit in MODE 3. Auxiliarv Feedwater (AFW) System and the Steam Generator (SG) safety valves can be used to remove core decay heat and meet all safety requirements." Hence, DCPP is considered to be a Hot Standby plant.

(5) 10006620.1ST 40MIS 6

CI PACIFIC GAS & ELECTRIC COMPANY i'

DIABLO CANYON POWER PLANT - UNITS I & 2 INSERVICE TESTING PROGRAM PLAN - PUMPS TABLE 1.0 REV 20 (2003)

ASME/ANSI OM-1987 (INCLUDING OMa-1988 ADDENDA) PAGE I OF 2 The attached sheets identify the pumps that are subject to the testing requirements of OMa 1988, Part 6, and the requests for relief from code requirements.

LEGEND:

CODE CLASS ASME Code Class taken from DWG 102028 Revision 21 (104628 Rev. 19 for Unit 2), "ASME CODE BOUNDARIES FOR INSERVICE INSPECTION AND TESTING PROGRAM."

TEST FREQUENCY NOTATION Notation Frequency IM At least once per 31 days Q At least once per 92 days A At least once per 366 days NA Not applicable TEST PARAMETER NOTATION Notation Parameter N Pump Speed (if variable speed)

Dp Pump Differential Pressure Q Flow Rate V Pump Vibration P Pump Discharge Pressure 10006620.1ST 40MIS 7

C C C PACIFIC GAS & ELECTRIC COMPANY DIABLO CANYON POWER PLANT - UNITS 1 & 2 INSERVICE TESTING PROGRAM PLAN - PUMPS TABLE 1.0 REV 20 (2003)

ASME/ANSI OM-1987 (INCLUDING OMa-1988 ADDENDA) PAGE 2 OF 2 P&ID CODE TEST PARAMETERS AND FREQUENCY RELIEF REMARKS PUMP NAME AND NUMBER COORD CLASS PROCEDURE N Dp P Q V REQUEST Safety Injection Pump I 57-E 2 P-SIP NA Q NA Q Q *Dp 2 1455 psid Safety Injection Pump 2 57-D 2 P-SIP NA Q NA Q Q *Dp 2 1455 psid Centrifugal Charging Pump I 43D-C 2 P-CCP NA Q NA Q Q *Dp 2 2400 psid Centrifugal Charging Pump 2 431D- 2 P-CCP NA Q NA Q Q *Dp 2 2400 psid Residual Heat Removal Pump I 36-D 2 P-RHR NA Q NA Q Q *Dp 165 psid Residual Heat Removal Pump 2 36-A 2 P-RHR NA Q NA Q Q, *Dp a 165 psid Containment Spray Pump I 36-D 2 P-CSP NA Q NA Q Q *Dp 2 205 psid Containment Spray Pump 2 36-A 2 P-CSP NA Q NA Q Q *DP > 205 psid Auxiliary Feed Pump 2 (Mtr) 43-D 3 P-AFW NA Q NA Q Q Auxiliary Feed Pump 3 (Mtr) 43-D 3 P-AFW NA Q NA Q Q Auxiliary Feed Pump I (Turb) 43-C 3 P-AFW Q Q NA Q Q RR2 Auxiliary Saltwater Pump I 31 B-A 3 P-ASW NA Q NA Q Q RR5 Auxiliary Saltwater Pump 2 31B-C 3 P-ASW NA Q NA Q Q RR5 Component Cooling Water Pump I 50-D 3 P-CCW NA Q NA Q Q RR4 Component Cooling Water Pump 2 52-D 3 P-CCW NA Q NA Q Q RR4 Component Cooling Water Pump 3 54-D 3 P-CCW NA Q NA Q Q RR4 Boric Acid Transfer Pump I 52B-A 2 P-BAT NA Q NA Q Q Boric Acid Transfer Pump 2 52B-B 2 P-BAT NA Q NA Q Q MU Water Transfer Pump 01 73-D 3 P-MUW NA Q NA Q Q, MU Water Transfer Pump 02 76-D 3 P-MUW NA Q NA Q Q

• Per Tech Spec Bases 10006620.1ST 40MIS 8

a. C C PACIFIC GAS & ELECTRIC COMPANY DIABLO CANYON POWER PLANT - UNITS I & 2 INSERVICE TESTING PROGRAM PLAN - PUMPS TABLE 1.1 REV 20 (2003)

ASME/ANSI OM-1987 (INCLUDING OMa-1988 ADDENDA) PAGE I OF 8 RELIEF REQUEST COMPONENT RELIEF REQUEST APPROVAL STATUS P-RRI All Pumps in IST Program Denied, NRC Letter dated 06/24197 P-RR2 Turbine-driven Auxiliary Feedwater Pumps Approved, NRC Letter dated 03/19/98 P-RR3 Centrifugal Charging Pumps Deleted, Design Change eliminated need P-RR4 Component Cooling Water Pumps Approved, NRC Letter dated 02/25/98 P-RR5 Auxiliary Saltwater Pumps Approved, NRC Letter dated 12/30/98 I

10006620.1ST 40MIS 9

PACIFIC GAS & ELECTRIC COMPANY DIABLO CANYON POWER PLANT - UNITS I & 2 INSERVICE TESTING PROGRAM PLAN - PUMPS AND VALVES TABLE 1.1 ASME/ANSI OM-1987 (INCLUDING OMa-1988 ADDENDA) REV 20 (2003)

REQUESTS FOR RELIEF FROM CODE REQUIREMENTS PAGE 2 OF 8 NO. P-RR2 Pumps: Turbine-driven Auxiliary Feedwater Pump I- I Turbine-driven Auxiliary Feedwater Pump 2-1 Code Class: 3 Test Reqt: Part 6; Section 6. 1, "Acceptance Criteria" states "If deviations fall within the alert range of Table 3, the frequency of the testing...shall be doubled...."

According to Table 3a, for centrifugal pumps with speeds

>600 rpm, any measured vibration levels greater than 0.325 in/sec fall within the Alert Range. Relief is requested from the 0.325 in/sec alert range value.

Functions:

The auxiliary feedwater (AFW) system provides a backup source of feedwater to the secondary side of the steam generators (SGs) when the main feedwater system is unavailable. This maintains the heat removal capability of the SGs. The system also functions as a source of feedwater during plant startups and shutdowns. The turbine-driven AFW pumps (AFWPs) are used as back up to the motor-driven AFWPs.

The turbine-driven AFWPs are tested on recirculation flow in accordance with ASME/ANSI OMa- 1988 and Technical Specification SR 3.7.5.2.

Basis:

PG&E requests relief based on 10CFR50.55a(a) (3) (i). The alternative testing provides an acceptable level of quality and safety.

Baseline testing and subsequent quarterly testing of the turbine-driven AFWPs is performed while on recirculation because the only other available flow path is into the steam generators which could result in thermal cycling of FW/AFW nozzles. The baseline vibration levels for the outboard pump bearings were measured at 0.312 in/sec for pump 1-1 and 0.316 in/sec for pump 2-1 in February 1992. The baseline vibration levels were investigated and the pumps were found to be operating acceptably. Subsequent testing on a monthly basis has shown that there is no increasing trend in vibration levels. Some data scatter occurs which occasionally results in vibration readings in the alert range of 0.325 in/sec to 0.700 in/sec. The upper limit of the observed vibration data scatter is approximately 0.400 in/sec. Analert level of 0.450 in/sec will prevent normal vibration from putting the pump on alert, yet it will still provide sufficient warning if the pump trends toward the action limit.

10006620.1ST 40MIS 10

PACIFIC GAS & ELECTRIC COMPANY DIAB3LO CANYON POWER PLANT - UNITS I & 2 INSERVICE TESTING PROGRAM PLAN - PUMPS AND VALVES TABLE 1.1 ASME/ANSI OM-1987 (INCLUDING OMa-1988 ADDENDA) REV 20 (2003)

REQUESTS FOR RELIEF FROM CODE REQUIREMENTS PAGE 3 OF 8 NO. P-R112 (cont)

Per the ASME Code, any vibration level greater than 0.325 in/sec is within the alert range and requires doubling the pump's testing frequency. Since these pumps were baselined, subsequent tests have yielded vibration levels averaging 0.248 in/sec for Unit I and 0.317 in/sec for Unit 2. To further investigate this vibration issue, vibration readings were taken on Pump 2-1 at full flow condition. The vibration levels dropped from >0.300 in/sec on recirculation to 0.099 in/sec at full flow.

Vibration spectral analysis indicates that the p.edominant frequency is five times pump speed which correlates with the pump vane pass frequency because the pump impellers have five vanes each. When the pumps are operated at low flow, during surveillance testing, the relative flow to the impeller is not aligned with the impeller vane. This causes vibration at vane passing frequency (5X). The operating design flow of these pumps is 870 gpm. Due to thermal fatigue and plant transient concerns, the surveillance test is run with the pump on recirculation flow of approximately 50 gpm.

These recirculation vibration levels do not warrant doubling the testing frequency. In addition, industry experience has shown that extended or frequent operation at minimum flow can cause pumps to degrade. In the case of the turbine-driven AFWPs, vibration at an alert level of 0.325 in/sec when tested on recirculation is not indicative of a potential pump problem.

Operation of the pumps at vibration levels of up to 0.45 in/sec for short periods of time during quarterly pump testing will not cause the pump to degrade. When the pumps are operated for normal and emergency operations, the flows will be higher and the vibration significantly reduced.

Alternative:

PG&E will set the vibration alert level to 0.450 in/sec for the turbine-driven AFWP bearings for pump testing on recirculation flow. The current action level of 0.700 in/sec will remain unchanged. The vibration levels will continue to be evaluated to the 0.325 in/sec alert level during full flow testing.

Full flow vibration testing will be performed on a COLD SHUTDOWN frequency not to exceed once per 92 days. The test will be performed in Mode 1, 2 or 3 when adequate steam flow is available. During the test, only the bearings which have had vibration levels greater than 0.325 in/sec during the quarterly tests will be monitored, in order to decrease the length of time that cold water is injected into the steam generators.

10006620.1ST 40MIS II

PACIFIC GAS & ELECTRIC COMPANY DIABLO CANYON POWER PLANT - UNITS & 2 INSERVICE TESTING PROGRAM PLAN - PUMPS AND VALVES TABLE 1.1 ASME/ANSI OM-1987 (INCLUDING OMa-1988 ADDENDA) REV 20 (2003)

REQUESTS FOR RELIEF FROM CODE REQUIREMENTS PAGE 4 OF 8 NO. P-RR4 System: Component Cooling Water Pumps: Code Class: P&EID Coordinate Component Cooling Water Pump 1-1 3 102028 E-250 Component Cooling Water Pump 1-2 3 102028 E-252 Component Cooling Water Pump 1-3 3 102028 E-254 Component Cooling Water Pump 2-1 3 104628 E-250 Component Cooling Water Pump 2-2 3 104628 E-252 Component Cooling Water Pump 2-3 3 104628 E-254 Functions:

The component cooling water (CCW) system removes heat from safety-related and nonsafety-related system components during normal operation and plant shutdown and transfers it to the ultimate heat sink via the auxiliary saltwater (AWS) system. The CCW pumps (CCWPs) are horizontally mounted centrifugal pumps.

The CCW system provides for safe shutdown and cooldown of the reactor by removing heat from safety-related and nonsafety-related system components after normal reactor shutdown, and from vital system components after an accident leading to an emergency shutdown.

Test Requirement Operation and Maintenance (OM) Part 6, para 5.2.(b), during pump test resistance of the system, shall be varied until flow equals the reference value.

Basis For Relief A variable flow measurement for the CCWP test is required because it is impractical to establish a fixed reference value(s). Relief is requested per IOCFR50.55a(f) (5) (iii). Diablo Canyon Power Plant (DCPP) had previously received relief for these pumps in the first 10 year plan.

10006620.1ST 40MIS 12

PACIFIC GAS & ELECTRIC COMPANY DIABLO CANYON POWER PLANT - UNITS I & 2 INSERVICE TESTING PROGRAM PLAN - PUMPS AND VALVES TABLE 1.1 ASME/ANSI OM-1987 (INCLUDING OMa-1988 ADDENDA) REV 20 (2003)

REQUESTS FOR RELIEF FROM CODE REQUIREMENTS PAGE 5 OF 8 NO. P-RR4 (cont.)

The CCW system has varying heat loads, and therefore varying flow requirements. A full flow test line with a single throttle valve for the purpose of testing was not incorporated in the initial design of the system. For some plant conditions, a reference flow condition cannot be established without adversely affecting the system flow balance and Technical Specification (TS) operability requirements. Thus, these pumps must be tested in a manner that the CCW system remains properly flow balanced during and after the testing and each supplied load remains fully operable per TS to maintain the required level of plant safety during power operation. During refueling outages, CCW flow demand varies greatly due to reactor coolant system cooldown, clearing of components for maintenance, and spent fuel pool heat exchanger cooling water demand. Past experience at DCPP has shown that CCW flow during refueling outages is usually greater than flow during power operations and it is not practical to reduce flow in order to perform the CCWP IST.

At a minimum, perturbation of multiple systems is required to establish a flow point due to the multiple flow paths of the CCW system. This abnormal configuration would have to be maintained for the length of time required to take vibration data and pump hydraulic data. In addition, the requirement for the Operators to manipulate valves required to adjust CCW flow to the reference point is adverse to ALARA.

Alternative Test Perform inservice tests on CCWPs using guidance from NUREG-1482, paragraph 5.2. A reference pump curve (flow rate vs. pump head) has been developed for each of the six CCWPs.

The following elements will be performed in developing the pump curves for testing the CCWPs. Existing ij ydata may be used in developing the curves provided it meets the criteria below.

I. Pump reference curves will be developed when the pumps are known to be operating satisfactorily.

2. Instrumentation used to develop pump curves is at least as accurate (accuracy and range) as required by OM Part 6, Table 1.

3. Pump curves will be constructed using a minimum of five points.

4. Points used to construct the curves are beyond the flat portion (low flow rates) of the pump curve in a range which includes the design bases flow rate.

5. Acceptance criteria for flow rate and differential pressure will be established by taking the more conservative of curves based on the limits of OM Part 6, Table 3b, or the operability criteria in TS or Safety Analysis Report.

6. Vibration levels will be measured over the range of pump conditions, and appropriate vibration acceptance criteria based on OM Part 6, Table 3a, will be assigned for regions of the pump curve.

7. A new reference curve will be prepared, or the previous curve will be validated, if the pump curve is affected by replacement, repair, or routine service.

10006620.1ST 40MIS 13

PACIFIC GAS & ELECTRIC COMPANY DIABLO CANYON POWER PLANT - UNITS I & 2 INSERVICE TESTING PROGRAM PLAN - PUMPS AND VALVES TABLE 1.1 t) jASME/ANSI OM-1987 (INCLUDING OMa-1988 ADDENDA) REV 20 (2003)

REQUESTS FOR RELIEF FROM CODE REQUIREMENTS PAGE 6 OF 8 NO. P-RR4 (coni)

References DCPP Final Safety Analysis Report Update Docket Numbers 50.275 and 50-323; Section 9.2.2 Component Cooling Water System.

DCPP Units I and 2 Technical Specification Bases for SR 3.6.6.3.

NUREG-1482 "Guidelines for Inservice testing at Nuclear Power Plants."

DCPP Supplemental Safety Evaluation Number 31, "Appendix A, Safety Evaluation Pump and Valve Inservice Testing Program," paragraph 2.3.3, "Relief Request (3)."

10006620.1ST 40MIS 14

PACIFIC GAS & ELECTRIC COMPANY DIABLO CANYON POWER PLANT - UNITS I & 2 INSERVICE TESTING PROGRAM PLAN - PUMPS AND VALVES TABLE 1.1 ASME/ANSI OM-1987 (INCLUDING OMa-1988 ADDENDA) REV 20 (2003)

REQUESTS FOR RELIEF FROM CODE REQUIREMENTS PAGE 7 OF 8 NO. P-RRS System: Auxiliary Saltwater Pumps: Code Class: P&ED Coordinate AuxiliarySaltwaterPump 1-1 3 102028 B-351 Auxiliary Saltwater Pump 1-2 3 102028 C-354 Auxiliary Saltwater Pump 2-1

• 3 104628 E-350 Auxiliary Saltwater Pump 2-2 3 104628 C-350 Functions:

The auxiliary saltwater (ASW) system supplies cooling water from the ultimate heat sink, the Pacific Ocean, to the component cooling water (CCW) heat exchangers. The CCW system, in turn, removes heat from nuclear primary plant equipment and components during normal plant operation, plant cooldowns, refueling and accident conditions, including a loss of coolant accident.

Each DCPP unit is provided with two redundant ASW trains. Each of these trains consist of a full capacity ASW pump (ASWP) and associated piping to supply the tube side of one of the CCW heat exchangers with cooling water. Each pump may also be cross-connected so as to supply the opposite train heat exchanger.

Test Requirement OM Part 6, para 5.2.(b), during pump test, resistance of the system shall be varied until flow equals the reference value.

Basis For Relief Adjustment to a specific reference value for the ASWP test is not practical because the pump flow rate varies based on tide level (suction pressure) and heat exchanger differential pressire (system resistance),

which cannot be readily controlled. The CCW heat exchanger outlet throttle valves are the only valves which can be adjusted to set ASWP flow at the desired test flow. These valves are sealed in a throttled position which ensures the train can perform its required safety function under worst case conditions. A CCW heat exchanger is considered inoperable after its outlet valve is adjusted until a flow verification test is performed. The flow verification test requires that the system alignment with the most system resistance i.e.,

ASW pump # I to CCW heat exchanger #2 (or ASW pump #2 to CCW heat exchanger # 1) be used. This realignment, test and subsequent data analysis takes several hours, during which time the CCW heat exchanger is inoperable. Diablo Canyon Technical Specifications require that the second vital CCW heat exchanger be placed in service whenever ultimate heat sink temperature is greater than 641F. In order to meet the Technical Specification LCO, ASW pump tests performed when ultimate heat sink temperatures are above 641F must be performed with two CCW heat exchangers in service and result in test flows of up to 14,000 gpm. When the test is run with only one CCW heat exchanger in service (normal test alignment),

reference pump flow is between 11,500 and 12,500 gpm. Relief is requested per IOCFR50.55a(f) (5) (iii).

10006620.1ST 40MIS 15

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REQUESTS FOR RELIEF FROM CODE REQUIREMENTS PAGE 8 OF 8 NO. P-RR5 (cont)

Alternative Test Perform inservice tests on ASWPs using guidance from NUREG-1482, paragraph 5.2. A reference pump curve (flow rate vs. pump head) will be developed for each of the four ASWPs.

The following elements will be performed in developing the pump curves for testing the ASWPs:

1. Pump reference curves will be developed vhen the pumps are known to be operating satisfactorily.

2. Instrumentation used to develop pump curves is at least as accurate (accuracy and range) as required by OM Part 6, Table 1.

3. These pump curves will be constructed using a minimum of five points.

4. Points used to construct the curves are beyond the flat portion (low flow rates) of the pump curve in a range which includes the design bases flow rate.

5. Acceptance criteria for flow rate and differential pressure will be established by taking the more conservative of curves based on the limits of OM Part 6, Table 3b, or the operability criteria in TS or Safety Analysis Report.

6. Vibration levels will be measured over the range of pump conditions, and appropriate vibration acceptance criteria based on OM Part 6, Table 3a, will be assigned for regions of the pump curve.

7. A new reference curve will be prepared, or the previous curve will be validated, if the pump curve is affected by replacement, repair, or routine service.

References DCPP Final Safety Analysis Report Update Docket Numbers 50.275 and 50-323; Section 9.2.2 Component Cooling Water System.

DCPP Units I and 2 Technical Specification 3.7.8.

NUREG- 1482 "Guidelines for Inservice testing at Nuclear Power Plants."

10006620.1ST 40MIS 16

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ASME/ANSI OM-1987 (INCLUDING OMa-1988 ADDENDA) PAGE I OF 52 The attached sheets identify the system valves that are subject to the testing requirements of OMa- 1988, Parts I and 10. and the requests for relief from code requirements.

LEGEND:

VALVE CLASS (VLV CLS)

ASME code class taken from DWG 102028 Revision 53 (104628 Rev. 47 for Unit 2) "ASME CODE BOUNDARIES FOR INSERVICE INSPECTION AND TESTING PROGRAM."

NOTE: TS indicates a non ASME code class valve that isrequired to be tested by Technical Specification.

IWV indicates a non ASME code class valve that is required to be tested in accordance with ASME Section Xi, Subsection IWV.

VALVE CATEGORY (VLV CAT)

OM Part 10, paragraph 1.4 VALVE CATEGORIES VALVE SIZE (VLV SIZ)

ASME SIZE IN INCHES VALVE TYPE (VLV TYP) NOTATION NOTATION TYPE BA Ball Valve BV Butterfly Valve CK Check Valve DI Diaphragm Valve GA Gate Valve GL Globe Valve PL Plug Valve RV Relief Valve 10006620.1ST 40MIS 17

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ASME/ANSI OM-1987 (INCLUDING OMa-1988 ADDENDA) PAGE 2 OF 52 LEGEND: (Continued)

ACTUATOR TYPE (ACT TYP) NOTATION NOTATION TYPE A Air Operated E Electric Motor H Electrohydraulic M Manual N None S Solenoid Operated NORMAL POSITION (NRM POS) NOTATION NOTATION POSITION 0 Open C Closed LO Locked, Sealed, or De-energized (Breaker Open) Open LC Locked, Sealed, or De-energized (Breaker Open) Closed V Variable 10006620.1ST 40MIS 18

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ASME/ANSI OM-1987 (INCLUDING OMa-1988 ADDENDA) PAGE 3 OF 52 LEGEND: (Continued)

TEST REQU IREMENT (TEST REQ) NOTATION NOTATIOJ REQUIREMENT EC Exercise of Check Valve - Full Stroke EF Exercise of Valve - Full Stroke EP Exercise of Check Valve or Valve - Partial Stroke EM Manual Exercise of Check Valve/Disassembly Inspection EN Nonintrusive Exercise of Check Valve LT Valve Leak Test Pi Position Indication Test RT Test Per OM Part 1 for Safety and Relief Valve NOTE: Valve Fail Safe testing is required by OM Part 10, paragraph 4.2.1.6. Valves with Fail Safe actuators are tested by the full stroke tests of the valves. A specific Test Requirement was not created for Fail Safe tests.

TEST FREQUENCY (TEST FRQ) NOTATION NOTATION FREQUENCY Q At least once per 92 days.

CS At least each cold shutdown but not more frequently than once per 92 days.

(This notation identifies valves that cannot be exercised during plant operation. A statement of the technical justification for not full stroke exercising these valves during plant operation is included in Table 2. 1).

R At least once per each refueling interval.

(This notation identifies valves that cannot be exercised during plant operation nor full stroke exercised during cold shutdown. A statement of the technical justification for not fill stroke exercising these valves during plant operation and whether they will be part stroked or not tested at all during cold shutdown is included in Table 2.2).

2Y At least once per 24 months.

T Per ASME/ANSI OM Part 1.

RR Tested on a rotational basis during refueling outages.

J Per IOCFR50 Appendix J, Option B.

S At least once per 184 days 10006620.1ST 40MIS 19

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ASME/ANSI OM-1987 (INCLUDING OMa-1988 ADDENDA) PAGE 4 OF 52 LEGEND: (Continued)

STROKE TIME (STR TIM)

For power operated valves, the maximum allowed stroke time is given in seconds followed by a "c" for closing, or an "o" for opening, or an 'o/c" for. both opening and closing. For manual valves and check valves, this column denotes that the valve has a safety function in the "c" closed position, in the "o' open position, or in both the o/c" open and closed position.

RELIEF REQUEST (REL REQ)

Numbers in this column refer to either a cold shutdown justification (CS), a refueling outage justification (RO), or a relief request (RR). These justifications and relief requests are found in TABLES 2.1, 2.2, and 2.3 respectively.

PROCEDURE NUMBER (PROC NO.)

Identifies procedure used to meet test requirement.

REMARKS The numbers in the remarks column refer to the list of remarks on the last page of TABLE 2.0.

DRAWING REFERENCE NUMBERS UNIT 1: 1020-series UNIT 2: 1080-series UNIT 2 SPECIFIC INFORMATION INDICATED BY PARENTHESES 10006620.1ST 40MIS 20

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ASME/ANSI OM-1987 (INCLUDING OMa-1988 ADDENDA) PAGE S OF 52 FEEDWATER SYSTEM P& ID NO. 1020 03 VALVE VALVE P& ID VLV VLV VLV VLV ACT NRM TST TST STR REL PROC NUMBER DESCRIPTION COORD CLS CAT SIZ TYP TYP POS REQ FRQ TIM REQ NO. REMARKS FW-348 AUX FP-I SUCT CK FROM CST 42-C 3 C 8 CK N C EP Q o P-AFW # I-BACKFLOW U S EC CS o CS2 P-AFW FW-349 AUX FP- I SUCT CK FROM RWS 41-C 3 C 8 CK N C EM RR o RRI V-18 FW-350 AUX FP-2 SUCT CK FROM CST 42-D 3 C 6 CK N C EP Q o P-AFW #I-BACKFLOW EC CS o CS2 A-AFW FW-352 AUX FP-3 SUCT CK FROM CST 42-D 3 C 6 CK N C EP Q o P-AFW #1-BACKFLOW EC CS o CS2 P-AFW FW-353 AUX FP-2&3 SUC CK FROM RWS 41-D 3 C 8 CK N C EM RR o RRI V-18 FW-354 AUX FP-I RECIRC CK 43-C 3 C 1.5 CK N C EC Q o P-AFW FW-355 AUX FP-2 RECIRC CK 43-D 3 C 1.5 CK N C EC Q o P-AFW FW-356 AUX FP-3 RECIRC CK 44-D 3 C 1.5 CK N C EC Q o P-AFW FW-361 AUX FP-I DISCH CK 44-C 3 C 6 CK N C EP Q o P-AFW #2-BACKFLOW EC CS o CS3 P-AFW FW-362 AUX FP-2 DISCH CK 44-D 3 C 4 CK N C EP Q o P-AFW #2-BACKFLOW EC CS o CS3 P-AFW FW-363 AUX FP-3 DISCH CK 44-D 3 C 4 CK N C EP Q o P-AFW #2-BACKFLOW EC CS o CS3 P-AFW FW-367 SG-2 FW CK 47-A 2 A,C 16 CK N 0 EC CS c CS1 V-3P3 LT 2Y c V-3P3 #3-ADMIN FW-368 SG-I FW CK 47-A 2 A,C 16 CK N 0 EC CS c CSI V-3P3 LT 2Y c V-3P3 #3-ADMIN FW-369 AUX FP- I TO SG-1 CK 47-C 2 C 3 CK N C EP Q o/c P-AFW EC CS o/c CS3 P-AFW 10006620.1ST 40MIS 21

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ASME/ANSI OM-1987 (INCLUDING OMa-1988 ADDENDA) PAGE 6 OF 52 FEEDWATER SYSTEM P& ID NO. 1020 03 VALVE VALVE P&ID V'LV VLV VLV VLV ACT NRM TST TST STR REL PROC NUMBER DESCRIPTION COORD CLS CAT SIZ TYP TYP POS REQ FRQ TIM REQ NO. REMARKS FW-370 AUX'FP-2 TO SG-1 CK 47-D 2 C 3 CK N C EP Q o/c P-AFW EC CS o/c CS3 P-AFW FW-371 AUX FP-I TO SG-2 CK 47-C 2 C 3 CK N C EP Q o/c P-AFW EC CS o/c CS3 P-AFW FW-372 AUX FP-2 TO SG-2 CK 47-D 2 C 3 CK N C EP Q o/c P-AFW EC CS o/c CS3 P-AFW FW-373 AUX FP-I TO SG-3 CK 47-B 2 C 3 CK N C EP Q c.c P-AFW EC CS o/c CS3 P-AFW FW-374 AUX FP-3 TO SG-3 CK 47-C 2 C 3 CK N C EP Q o/c P-AFW EC CS o/c CS3 P-AFW FW-375 AUX FP-I TO SG-4 CK 47-B 2 C 3 CK N C EP Q o/c P-AFW EC CS o/c CS3 P-AFW FW-376 AUX FP-3 TO SG-4 CK 47-C 2 C 3 CK N C EP Q o/c P-AFW EC CS o/c CS3 P-AFW FW-377 SG-I AUX FW ISTCK 49-B 2 C 3 CK N C EP Q 0 P-AFW EC CS 0 CS3 P-AFW FW-378 SG-2 AUX FW I ST CK 48-B 2 C 3 CK- N C EP Q 0 P-AFW EC CS 0 CS3 P-AFW FW-379 SG-3 AUX FW I ST CK 48-B 2 C 3 CK N C EP Q 0 P-AFW EC CS 0 CS3 P-AFW FW-380 SG-4 AUX FW IST CK 48-B 2 C 3 CK N C EP Q 0 P-AFW EC CS o CS3 P-AFW 10006620.1ST 40MIS 22

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ASME/ANSI OM-1987 (INCLUDING OMa-1988 ADDENDA) PAGE 7 OF 52 FEEDWATER SYSTEM P& ID NO. 1020 03 VALVE VALVE P& ID VLV VLLV VLV VLV ACT NRM TST TT STR REL PROC NUMBER DESCRIPTION COORD CLS CAT SIZ TYP TYP POS REQ FRQ TIM REQ NO. REMARKS FW-531 SG-3'FW CK 47-A 2 A,C 16 CK N 0 EC CS c CS 1 V-3P3 LT 2Y c V'3P3 #3-ADMIN FW-532 SG-4 FW CK 47-A 2 A,C 16 CK N 0 EC CS c CS 1 V-3P3 LT 2Y V-3P3 #3-ADMIN FCV-436 RWS SUP AUX FP-I 41-C 3 B 8 BV M C EF Q2 o/c V-3P4 *PerTech Spec FCV-437 RWS SUP AUX FP-2 & 3 41-D 3 B 8 BV M C EF Q* o/c V-3P4 *Per Tech Spec FCV-438 SG-I FW ISO 48-A 2 B 16 GA E 0 PI 2Y NA V-2UIC EF CS 60c CS I V-3P2 FCV-439 SG-2 FW ISO 47-A 2 B 16 GA E 0 Pi 2Y NA V-2U2C EF CS 60c CS1 V-3P2 FCV-440 SG-3 FW ISO 47-A 2 B 16 GA E 0 Pl 2Y NA V-2U3C EF- CS 60c CS 1 V-3P2 PCV-441 SG-4 FW ISO 48-A 2 B 16 GA E 0 Pl 2Y NA V-2U4C EF CS 60c CS I V-3P2 LCV-106 AUX FP-I TO SG-I REG 47-C 2 B 3 GL E 0 Pl 2Y NA V-2UID EF Q 20o/c V.3P5 LCV-107 AUX FP-I TO SG-2 REG 47-C 2 B 3 GL E 0 Pl 2Y NA V-2U2D EF Q 20o/c V-3P5 LCV-108 AUX FP-I TO SG-3 REG 47-B 2 B 3 GL E 0 Pi 2Y NA V-2U3D EF Q 200/c V-3P5 LCV-109 AUX FP-I TO SG-4 REG 47-B 2 B 3 GL E 0 Pl 2Y NA V-2U4D EF Q 20o/c V-3P5 LCV-1 10 AUX FP-2 TO SG-I REG 47-D 2 B 2 GL H 0 P1 2Y NA V-2UID EF Q 40o/c V-3P6A LCV-I I AUX FP-2 TO SG-2 REG 47-D 2 B 2 GL H 0 P1 2Y NA V-2U2D EF Q 40o/c V-3P6A 10006620.1ST 40MIS 23

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ASME/ANSI OM-1987 (INCLUDING OMa-1988 ADDENDA) PAGE 8 OF 52 FEEDWATER SYSTEM P& ID NO. 1020 03 VALVE VALVE P&ID VLV VLV VLV VLV ACT NRM TST TST STR REL PROC NUMBER DESCRIPTION COORD CLS AT SIZ TYP TYP POS REQ FRQ TIM REQ NO. REMARKS LCV-1 13 AUXFP-3 TO SG-4 REG 47-C 2 B 2 GL H O Pi 2Y NA V-2U4D EF Q 40O/c V-3P6B LCV-1 15 AUX FP-3 TO SG-3 REG 47-C 2 B 2 GL H O Pi 2Y NA V-2U3D EF Q 40o/c V-3P6B FCV-510 SG-I FW REG 33A-E TS B 12 GL A O EF CS* 7c V-3PI *Per Tech Spec (38-C) Pl 2Y NA V-2UIC FCV-520 SG-2 FW REG 33A-D TS B 12 GL A O EF CS* 7" V-3PI *Per Tech Spec (38-D) P1 2Y NA V-2U2C FCV-530 SG-3 FW REG 33A-A TS B 12 GL A O EF CS* 7c V-3PM 'Per Tech Spec (38-E) Pl 2Y NA V-2U3C FCV-540 SG-4 FW REG 33A-C TS B 12 GL A O EF CS* 7c V-3PI *Per Tech Spec (38-D) Pl 2Y NA V-2U4C FCV-1510 SG-4 FW REG BYPASS 33A-E TS B 6 GL A C EF CS* 7c V-3PI *PerTech Spec (37-B) Pl 2Y NA V-2UIC FCV-1520 SG-2 FW REG BYPASS 33A-C TS B 6 GL A C EF CS* 7c V-3rP *Per Tech Spec (38-D) Pl 2Y NA V-2U2C FCV-1530 SG-3 FW REG BYPASS 33A-A TS B 6 GL A C EF CS* 7c V-3PI *PerTech Spec (38-E) Pl 2Y NA V-2U3C FCV-1540 SG-4 FW REG BYPASS 33A-B TS B . 6 GL A C EF CS* 7c V-3PI *PerTech Spec (38-E) Pl 2Y NA V-2U4C RV-536 AUX FP-1 SUCT RELIEF 42-C 3 C lxl.5 RV N C RT T NA M-77 1001 (42-D)

RV-537 AUX FP-2&3 SUCT RELIEF 41-D 3 C lxl.5 RV N C RT T NA M-77 100 10006620.1ST 40MIS 24

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ASME/ANSI OM-1987 (INCLUDING OMa-1988 ADDENDA) PAGE 9 OF 52 TURBINE STEAM SYSTEM P& ID NO. 1020 04 VALVE VALVE P & ID VLV VLV VLV VLV ACT NRM TST TST STR REL PROC NUMBER DESCRIPTION COORD CLS CAT SIZ TYP TYP POS REQ FRQ TIM REQ NO. REMARKS MS-1015 SG-I '10% STM DUMP ISO VALVE 63-B 2 B 8 GA M 0 EF Q NA V-3R1 MS-1068 SG- I MS LINE CK 31-A IWV C 28 CK N 0 EM R C ROI V-18 S-2015 SG-2 10% STM DUMP ISO VALVE 63-D 2 B 8 GA M 0 EF Q NA V-3R1 MS-2066 SG-2 MS LINE CK 31-B IWV C 28 CK N 0 EM R C ROl V-18 MS-3015 SG-3 10% STM DUMP ISO VALVE 53-C 2 B 8 GA M 0 EF Q NA V-3R1 MS-3062 SG-3 MS LINE CK 31-D IWV C 28 CK N 0 EM R C ROI V-18 MS-4015 SG4 10% STM DUMP ISO VALVE 53-D 2 B 8 GA M 0 EF Q NA V-3R1 MS-4062 SG-4 MS LINE CK 31-E IWV C 28 CK N 0 EM R C ROl V-18 MS-5166 SG-2 STM TO AUX FP-I CK 30-B 2 C 4 CK N C EP Q 0 P-AFW EC CS CS4 P-AFW EM RR c RRl V-18 MS-5167 SG-3 STM TO AUX FP-I CK 31-C 2 C 4 CK N C EP Q 0 P-AFW EC CS 0 CS4 P-AFW EM RR RR I V-18 FCV-22 SG-4 MSIV BYPASS 31-E 2 B 3 GL A C Pi 2Y Sc NA V-2U4A EF Q Sc V-3R4 FCV-23 SG-3 MSIV BYPASS 31-C 2 B 3 GL A C Pi 2Y NA V-2U3A EF Q Sc V-3R4 FCV-24 SG-2 MSIV BYPASS 31-B 2 B 3 GL A C Pi 2Y NA V-2U2A EF Q 5c V-3R4 FCV-25 SG- MSIV BYPASS 31-A 2 B 3 GL A C Pi 2Y NA V-2UIA EF Q 5c V-3R4 10006620.1ST 40MIS 25

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ASME/ANSI OM-1987 (INCLUDING OMa-1988 ADDENDA) PAGE OOF 52 TURBINE STEAM SYSTEM P& ID NO. 1020 04 VALVE VALVE P & ID VLV VLV VLV VLV ACT NRM TST TST STR REL PROC NUMBER DESCRIPTION COORD CLS CAT SIZ TYP TYP POS REQ FRQ TIM REQ NO. REMARKS FCV-37 SG-2 STM TO AUX FP- I 30-B 2 B 4 GA E 0 P1 2Y NA V-2U2E EF Q 30o/c V-3R6 FCV-38 SG-3 STM TO AUX FP-I 31-C 2 B 4 GA E 0 Pl 2Y NA V-2U3E EF Q 30O/c V-3R6 FCV-41 SG-1 MSIV 31-A *2 B 28 CK A 0 Pl 2Y NA V-2UIA EF CS 5c CS5 V-3R2 FCV-42 SG-2 MSIV 31-B 2 B 28 CK A 0 Pl 2Y i4A V-2U2A EF CS 5c CSS V-3R2 FCV-43 SG-3 MSIV 31-D 2 B 28 CK A 0 Pi 2Y NA V-2U3A EF CS Sc CS5 V-3R2 FCV-44 SG-4 MSIV 31-E 2 B 28 CK A 0 Pi 2Y NA V-2U4A EF CS Sc CSS V-3R2 FCV-95 AUX FP-I STM SUP 31-B 2 B 4 GA E C Pl 2Y NA V-2U5B EF Q 30o V-3R5 FCV-151 SG-I BD ISOL OC 72-C 2 B 3 GA A 0 P1 2Y NA V-2J4 EF Q lOc V-3S2 FCV-154 SG-2 BD ISOL OC 72-C 2 B 3 GA A 0 Pi 2Y NA V-2J4 EF Q 1Oc V-3S2 10006620.1ST 40MIS 26

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ASME/ANSI OM-1987 (INCLUDING OMa-1988 ADDENDA) PAGE 11 OF52 TURBINE STEAM SYSTEM P&ID NO. 1020 04 VALVE VALVE P&ID VLV VLV VLV VLV ACT NRM TST TST STR REL PROC NUMBER DESCRIPTION COORD CLS CAT SIZ TYP TYP POS REQ FRQ TIM REQ NO. REMARKS FCV-IS57 SG-3 BD ISOL OC 72-D 2 B 3 GA A 0 Pl 2Y NA V-2J4 EF Q 1Oc V-3S2 FCV-I( 60 SG-4 BD ISOL OC 72-E 2 B 3 GA A 0 Pl 2Y NA V-2J4 EF Q IOc V-3S2 FCV-2414 SG-4 SAMPLE ISOL OC 72-E 2 B ..75 GL A 0 Pi 2Y NA V-2J4 EF Q lOc V-3S2 FCV-24 16 SG-3 SAMPLE ISOL OC 72-D 2 B .75 GL A 0 Pl 21 NA V-2J4 EF Q lOc V-3S2 FCV-24 18 SG-2 SAMPLE ISOL OC 72-C 2 B .75 GL A 0 Pl 2Y NA V-2J4 EF Q 1Oc V-3S2 FCV-2550 SG-I SAMPLE ISOL OC 72-C 2 B .75 GL A 0 Pl 2Y NA V-2J4 EF Q IOc V-3S2 FCV-7( 60 SG- I BD ISOL IC 71-C 2 B .3 GL A 0 Pl 2Y NA V-2N I EF Q Sc V-3R3 FCV-76 1 SG-2 BD ISOL IC 71 -C 2 B 3 GL A 0 Pl 2Y NA V-2NI EF Q Sc V-3R3 FCV-7f 62 SG-3 BD ISOL IC 71-D 2 B 3 GL A 0 Pi 2Y NA V-2NI EF Q Sc V-3R3 FCV-7663 SG-4 BD ISOL IC 71-E 2 B 3 GL A 0 Pl 2Y NA V-2N I EF Q 5c V-3R3 PCV-I9I SG- I 10% ATM DUMP 30-A 2 B 8 GL A C Pl 2Y NA V-2UI B

EF Q 20o/40c V-3RI 10006620.1ST 40MIS 27

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ASME/ANSI OM-1987 (INCLUDING OMa-1988 ADDENDA) PAGE 12 OF 52 TURBINE STEAM SYSTEM P& ID NO. 1020 04 VALVE VALVE P & ID VLV VLV VLV VLV ACT NRM TST TST STR REL PROC NUMBER DESCRIPTION COORD CLS CAT SIZ TYP TYP POS REQ FRQ TIM REQ NO. REMARKS PCV-20 SG-2 fO% ATM DUMP 30-C 2 B 8 GL A C P1 2Y NA V-2U2B EF Q 20o/40c V-3RI PCV-21 SG-3 10% ATM DUMP 31-D 2 B 8 GL A C P1 2Y NA V-2U3B EF Q 20o/40c V-3RI PCV-22 SG-4 10% ATM DUMP 31-E 2 B 8 GL A C Pi 2Y NA V-2U4B EF Q 20o/40c V-3R1 RV-3 SG-1 SAFETY 30-A 2 C 6 RV N C RT T NA M-77 1065#

RV.4 SG-I SAFETY 31-A 2 C 6 RV N C RT T NA M-77 1078#

RV-5 SG- SAFETY 31-A 2 C 6 RV N C RT T NA M-77 1090#

RV-6 SG-I SAFETY 31-A 2 C 6 RV N C RT T NA M-77 1103#

RV-7 SG-2 SAFETY 30-B 2 C 6 RV N C RT T NA M-77 1065#

RV-8 SG-2 SAFETY 31-B 2 C 6 RV N C RT T NA M-77 1078#

RV-9 SG-2 SAFETY 31-B 2 C 6 RV N C RT T NA M-77 1090ff RV-10 SG-2 SAFETY 31-B 2 C 6 RV N C RT T NA M-77 1103#

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ASME/ANSI OM-1987 (INCLUDING OMa-1988 ADDENDA) PAGE 13 OF 52 TURBINE STEAM SYSTEM P& ID NO. 1020 04 VALVE VALVE P&ID VLV VLV VLV VLV ACT NRM TST TST STR REL PROC NUMBER DESCRIPTION COORD CLS CAT SIZ TYP TYP POS REQ. FRQ TIM REQ NO. REMARKS RV-II SG- SAFETY 31-D 2 C 6 RV N C RT T NA M-77 1065#

RV-12 SG-3 SAFETY 31-D 2 C 6 RV N C RT T NA M-77 1078#

RV- 13 SG-3 SAFETY 32-D 2 C 6 RV N C RT T NA M-77 109o RV-14 SG-3 SAFETY 31-D 2 C 6 RV N C RT T NA M-77 1103#

RV-58 SG-4 SAFETY 31-E 2 C 6 RV N C RT T NA M-77 1065#

RV-59 SG-4 SAFETY 31-E 2 C 6 RV N C RT *T NA M-77 1078#

RV-60 SG-4 SAFETY 32-E 2 C 6 RV N C RT T i;A M-77 1090$

RV-61 SG-4 SAFETY 31-E 2 C 6 RV N C RT T NA M-77 1103#

RV-222 SG-I SAFETY 31-A 2 C 6 RV N C RT T NA M-77 11 15f RV-223 SG-2 SAFETY 31-B 2 C 6 RV N C RT T NA M-77 11 15#

RV-224 SG-3 SAFETY 31-D 2 C 6 RV N C RT T NA M-77 11 15#

RV-225 SG-4 SAFETY 31-E 2 C 6 RV N C RT T NA M-77 11 15#

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ASME/ANSI OM-1987 (INCLUDING OMa- 1988 ADDENDA) PAGE 14 OF 52 AUXILIARY STEAM SYSTEM P& ID NO. 1020 06 VALVE VALVE P & ID VLV VLV VLV VLV ACT NRM TST TST STR REL PROC NUMBER DESCRIPTION COORD CLS CAT SIZ TYP TYP POS REQ FRQ TIM REQ NO. REMARKS AXS-208 AXS STM SUP TO CONT ISO IC 43-E 2 A 2 CK N C LT J c V-670 AXS-26 AUX STM SUP TO CONT ISO OC 43-D 2 A 2 GA M LC LT J c V-670 10006620.IST . 40MIS 30

C C PACIFIC GAS & ELECTRIC COMPANY DIABLO CANYON POWER PLANT - UNITS 1 & 2 INSERVICE TESTING PROGRAM PLAN - VALVES TABLE 2.0 REV 20 (2003)

ASME/ANSI OM-1987 (INCLUDING OMa-1988 ADDENDA) PAGE 15 OF 52 REACTOR COOLANT SYSTEM P& ID NO. 1020 07 VALVE VALVE P &ID VLV VLV VLV VLV ACT NRM TST TST STR REL PROC NUMBER DESCRIPTION COORD CLS CAT SIZ TYP TYP POS REQ FRQ TIM REQ NO. REMARKS RCS-508 RV &STM LK OFF HDR TO PRT 44-E 3 C 4 CK N C EM R 0 R014 V-18 RV function RCS-512 MISC EQUIP DR TANK ISOL OC 48-A 2 A 3/4 GL M LC LT J c V-671 PCV455C PZR PORV 40-C I B 2 GL A C P1 2Y NA V-2TI EF CS 2.9o CS6 V-3J2 PCV-456 PZR PORV 40-B I B 2 GL A C Pi 2Y NA V-2TI EF CS 2.9o CS6 V-3J2 PCV-474 PZR PORV 40-C I B 2 GL A C Pi 2'i NA V-2TI EF CS 2.9o CS6 V-3J2 8000A PZR PORV ISOL 41-C I B 3 GA E 0 Pi 2Y NA V-2TI EF Q 20c V-3J1IA 800B PZR PORV ISOL 41-C I B 3 GA E 0 Pi 2Y NA V-2TI EF Q 20c V-3JIB 8000C PZR PORV ISOL 40-B I B 3 GA E 0 Pi 2Y NA V-2TI EF Q 20c V-3JIC 8010A PZR SAFETY 43-D I A,C 6 RV N C RT T NA M-77 2485#

8010B PZR SAFETY 43-D I A,C 6 RV N C RT T NA M-77 2485#,

8010C PZR SAFETY 42-D I AC 6 RV N C RT T NA M-77 2485#f 8028 RV DISC HDR TO PRT ISOL IC 47-C 2 A,C 4 CK N C LT J C V-671 EM R o/C R014 V-18 RV function 8029 PRI WTR TO PRT ISOL OC 48-D 2 A 3 BA A 0 Pi 2Y NA V-2J7 LT J C V-652A EF Q 1Oc V-3S7 10006620.1ST 40MIS 31

C r PACIFIC GAS & ELECTRIC COMPANY DIABLO CANYON POWER PLANT - UNITS I & 2 INSERVICE TESTING PROGRAM PLAN - VALVES TABLE 2.0 REV 20 (2003)

ASME/ANSI OM-1987 (INCLUDING OMa-1988 ADDENDA) PAGE 16 OF 52 REACTOR COOLANT SYSTEM P& ID NO. 1020 07 VALVE VALVE P & ID VLV VLV VLV VLV ACT NRM TST TST STR REL PROC NUMBER DESCRIPTION COORD CLS CAT SIZ TYP TYP POS REQ FRQ TIM REQ NO. REMARKS 8034A PRT TO GA ISOL IC 48-E 2 A 3/8 GL A 0 P1 2Y NA V-204 LT c V-676B EF Q 1oc V-3S8 8034B PRT TO GA ISOL OC 48-E 2 A 3/8 GL A C Pi 2Y NA V-2J7 LT J c V-676B EF .Q 1Oc V-3S8 8045 N2 TO PRT ISOL OC 48-E 2 A 3/4 Di A 0 Pi NA V-2J7 LT c V-652B EF Q lOc V-3S8 8046 PRI WTR TO PRT ISOL IC 48-D 2 A,C 3 CK N C LT R c V-652A EC R c RR2 V-652A 8047 N2 TO PRT ISOL IC 48-E 2 A,C 3/4 CK N C LT R c V-652B EC R c RR2 V-652B 8078A REACTOR VESSEL 75-B 2 B I GL S LC Pi 2Y NA V-2T2 HEAD VENT EF R 2o R021 V-2T2 8078B REACTOR VESSEL 75-B 2 B I GL S LC Pi 2Y NA V-2T2 HEAD VENT EF R 2o R021 V-2T2 8078C REACTOR VESSEL 75-B 2 B I GL S LC Pi . 2Y NA V-2T2 HEAD VENT EF R 2o R021 V-2T2 8078D REACTOR VESSEL 75-B 2 B I GL S LC Pi 2Y NA V-2T2 HEAD VENT EF R 2o R021 V-2T2 10006620.1ST 40MIS 32

C C C PACIFIC GAS & ELECTRIC COMPANY DIABLO CANYON POWER PLANT - UNITS I & 2 INSERVICE TESTING PROGRAM PLAN - VALVES TABLE 2.0 REV 20 (2003)

ASME/ANSI OM-1987 (INCLUDING OMa-1988 ADDENDA) PAGE 17 OF 52 CHEMICAL AND VOLUME CONTROL SYSTEM P& ID NO. 1020 08 VALVE VALVE P & ID VLV VLV VLV VLV ACT NRM TST TST STR REL PROC NUMBER DESCRIPTION COORD CLS CAT SIZ TYP TYP POS REQ FRQ TIM REQ NO. REMARKS FCV-110A BA SUP TO BLENDER 40B-B 2 B 2 GL A C Pl 2Y NA V-2K EF Q lOo V-3EI # - Hosgri LCV-112B VCTOUTISOL 43B-D IWV B 4 GA E O P1 2Y NA V-211 EF CS 10c CS8 V-3K12 LCV-112C VCTOUTISOL 43B-D IWV B 4 GA E O PI 2Y NA V-211 EF CS 10c CS8 V-3K12 8100 RCP SEAL WTR RETRN ISOL OC 39-E 2 A 4 GA E O PI 2Y NA V-211 LT J c V-645 EF CS 10c CS9 V-3K2 8104 EMERG BORATE 41B-A 2 B 2 GL E C Pl 2Y NA V-2K EF Q 10O V-3E5 8105 CENT CHG PP RECIRC 41B-A IWV B 2 GL E O P1 2Y NA V-211 EF CS 10c CS10 V-3K9 8106 CENT CHG PP RECIRC 41B-A 2 B 2 GL E O PI 2Y NA V-211 EF CS 10c CS10 V-3K9 8107 CHG LINE ISOL OC 47B-C 2 B 3 GA E O P1 2Y NA V-211 EF CS 14c CSI I V-3K13 8108 CHG LINE ISOL 47B-C 2 B 3 GA E O PI 2Y NA V-211 EF CS 14c CSI I V-3K13 8109 RCP SEAL WTR RETRN ISOL IC 38-D 2 A,C 3/4 CK N O LT R C V-645 EC R c RR2 V-645 EC R o RO 15 . V-645 RV function 10006620.1ST 40MIS 33

C (7 C PACIFIC GAS & ELECTRIC COMPANY DIABLO CANYON POWER PLANT - UNITS I & 2 INSERVICE TESTING PROGRAM PLAN - VALVES TABLE 2.0 REV 20 (2003)

ASME/ANSI OM-1987 (INCLUDING OMa-1988 ADDENDA) PAGE 8 OF 52 CHEMICAL AND VOLUME CONTROL SYSTEM P& ID NO. 1020 08 VALVE VALVE P &ID VLV VLV VLV VLV ACT NRM TST TST STR REL PROC NUMBER DESCRIPTION COORD CLS CAT SIZ TYP TYP POS REQ FRQ TIM REQ NO. REMARKS 8112 RCP SEAL WTR RETRN ISOL IC 38-E 2 A 4 GA E 0 PI 2Y NA V-211 LT J c V-645 EF CS lOc CS9 V-3K2 8145 PZR AUX SPRAY 43-D I B 2 GL A C PI 2Y NA V-2S EF CS 100 CS12 V-3K8 8146 NORMAL CHG 43-D 2 B 2 GL A 0 PI 2Y, NA V-2S EF CS 20o CS32 V-3K5 8147 ALTERNATE CHG 42-D 2 B 2 GL A C PI 2Y NA V-2S EF CS 20o CS32 V-3K5 8148 PZR AUX SPRAY BYP 43-D I B 2 GL A C PI 2Y NA V-2S EF CS oo CS12 V-3K8 8149A LTDN ORF RO-27 ISOL IC 43-C 2 A 2 GL A C PI 2Y NA V-2Y LT J c V-635 EF CS 10c CS30 V-3K7A 10006620.1ST 40MIS 34

C c C PACIFIC GAS & ELECTRIC COMPANY DIABLO CANYON POWER PLANT - UNITS I & 2 INSERVICE TESTING PROGRAM PLAN - VALVES TABLE 2.0 REV 20 (2003)

ASME/ANSI OM-1987 (INCLUDING OMa-1988 ADDENDA) PAGE 19 OF 52 CHEMICAL AND VOLUME CONTROL SYSTEM P& ID NO. 1020 08 VALVE VALVE P & ID VLV VLV VLV VLV ACT NRM TST TST STR REL PROC NUMBER DESCRIPTION COORD CLS CAT SIZ TYP TYP POS REQ FRQ TIM REQ NO. REMARKS 8149B LTDN ORF RO-27 ISOL IC 43-C 2 A 2 GL A 0 Pi 2Y NA V-2Y LT J c V-635 EF CS IOc CS30 V-3K7A 8149C LTDN ORF RO-27 ISOL IC 43-C 2 A 2 GL A C Pi 2Y NA V-2Y LT 3 c V-635 EF CS 10c CS30 V-3K7A 8152 LTDN LINE ISOL OC 44-C 2 A 2 GL A 0 Pi 2Y NA V-2J8 LT J c V-635 EF CS 10c CS13 V-3K7B 8367A RCP-I SEAL INJ 2ND CK IC 31-C I C 2 CK N O EC Q o M-54 8367B RCP-2 SEAL INJ 2ND CK IC 33-C I C 2 CK N O EC Q o M-54 8367C RCP-3 SEAL INJ 2ND CK IC 35-C I C 2 CK N O EC Q o M-54 8367D RCP-4 SEAL INJ 2ND CK IC 37-C I C 2 CK N O EC Q o M-54 8368A RCP- I SEAL INJ IST CK IC 30-B 2 A,C 2 CK N 0 LT R c V-641 EC R c RR2 V-641 EC Q o M-54 8368B RCP-2 SEAL INJ I ST CK IC 33-B 2 A,C 2 CK N 0 LT R c V-641 EC R c RR2 V-641 EC Q o M-54 8368C RCP-3 SEAL INJ 1ST CK IC 35-B 2 A,C 2 CK N O LT R c V-641 EC R c RR2 V-641 EC Q o M-54 8368D RCP-4 SEAL INJ IST CK IC 37-B 2 A,C 2 CK N 0 LT R c V-641 EC R c RR2 V-641 EC Q o M-54 10006620.1ST 40MIS 35

C.

r C PACIFIC GAS & ELECTRIC COMPANY DIABLO CANYON POWER PLANT - UNITS I & 2 INSERVICE TESTING PROGRAM PLAN - VALVES TABLE 2.0 REV 20 (2003)

ASME/ANSI OM-1987 (INCLUDING OMa-1988 ADDENDA) PAGE 20 OF 52 CHEMICAL AND VOLUME CONTROL SYSTEM P& ID NO. 1020 08 VALVE VALVE P & ID VLV VLV VLV VLV ACT NRM TST TST STR REL PROC NUMBER DESCRIPTION COORD CLS CAT SIZ TYP TYP POS REQ FRQ TIM REQ NO. REMARKS 0171A Dd'- I O0A I tMl D I Irf in I I' o d"p I n' ft PA K CA uj I4j1 RCP-2 OAL INJ jR CK IC u IVIs-it 8372B RCP-2 SEAL INJ 3RD CK IC 33-B 1 C 2 CK N 0 EC Q 0 M-54 8372C RCP-3 SEAL INJ 3RD CK IC 35-B I C 2 CK N 0 EC Q 0 M-54 8372D RCP-4 SEAL INJ 3RD CK IC 37-B I C 2 CK N 0 EC Q 0 M-54 8377 PZR AUX SPRAY CK 42-E I C 2 CK N C EC CS 0 CS12 V-3K8 8378A CHG TO LOOP 3 COLD LEG CK 41-E I C 3 CK N 0 EC CS .0 CS32 V-3K5 8378B CHG TO LOOP 4 COLD LEG CK 41-E I C 3 CK N 0 EC CS 0 CS32 V-3K5 8378C CHG LINE CK 43-B 2 C 3 CK N 0 EC CS 0 CS32 V-3K5 8379A CHG TO LOOP 3 COLD LEG CK 41-E I C 3 CK N 0 EC CS 0 CS32 V-3K5 8379B CHG TO LOOP 4 COLD LEG CK 41-E I C 3 CK N 0 EC CS 0 CS32 V-3K5 8440 VCT OUTLET CK 143-C 2 C 4 CK N 0 EC R c ROI IM-86G #7-OPEN 8445 EMER BORATE REV FLO CK 41B-B 2 C 2 CK N C EC Q 0 V-3E5 8475 RECIP CHG PP-3 DISCH CK 45B-C 2 C 2 CK N 0 EC Q 0 P-PDP EC R c R02 V-25 8478A CENT CHG PP- I DISCH CK 45B-B 2 C 4 CK N C EP Q 0 P-CCP EC R 0 R02 V-15 EC R c R02 V-25 8478B CENT CHG PP-2 DISCH CK 45B-A 2. C 4 CK N C EP Q 0 P-CCP EC R 0 R02 V-15 EC R c R02 V-25 10006620.1ST 40MIS 36

r C C, PACIFIC GAS & ELECTRIC COMPANY DIABLO CANYON POWER PLANT - UNITS I & 2 INSERVICE TESTING PROGRAM PLAN - VALVES TABLE 2.0 REV 20 (2003)

ASME/ANSI OM-1987 (INCLUDING OMa-1988 ADDENDA) PAGE 21 OF 52 CHEMICAL AND VOLUME CONTROL SYSTEM P& ID NO. 1020 08 VALVE VALVE P & ID VLV VLV VLV VLV ACT NRM TST TST STR REL PROC NUMBER DESCRIPTION COORD CLS CAT SIZ TYP TYP POS REQ FRQ TIM REQ NO. REMARKS 8479A CENT CHG PP-I RECIRC CK 44B-B 2 C 2 CK N C EC Q 0 P-CCP 8479B CENT CHO PP-2 RECIRC CK 45B-A 2 C 2 CK N C EC Q 0 P-CCP 8483 CHG FLO TO CL 3 BYPAS CK 42-E I C 3/4 CK N C EC R 0 R017 V-15 RV function 8487A BA TRANSFER PP-2 (PP- I) 52B-B 2 C 2 CK N 0 EC Q 0 P-BAT DISCH CK (57B-B) 8487B BA TRANSFER PP-I (PP-2) 52B-A 2 C 2 CK N 0 EC Q 0 P-BAT DISCH CK (57B-A)

RV-8116 PDP RV TO VCTI 44B-D 2 C 3/4xI RV N C RT T o M-77 2720#

RV-8117 LETDOWN RV TO PRT 44-C 2 C 2 RV N C RT T o M-77 600#

RV-8121 RCP SEAL WTR RETURN HDR RV 37-E 2 C 2 RV N C RT T o M-77 150#

RV-8123 SEAL WTR HXI INLT RV TO VCT 41B-D NA C 2 RV N C RT T o M-77 150#

RV-8125 CHG PPS SUC HDR REL TO PZR 40D-B 2 C 3/4 RV N C RT T 0 M-77 220#

(43B-B) 10006620.1ST 40MIS 37

r PACIFIC GAS & ELECTRIC COMPANY DIABLO CANYON POWER PLANT - UNITS I & 2 INSERVICE TESTING PROGRAM PLAN - VALVES TABLE 2.0 REV 20 (2003)

ASME/ANSI OM-1987 (INCLUDING OMa-1988 ADDENDA) PAGE 22 OF 52 SAFETY INJECTION SYSTEM P& IDNO. 102009 VALVE VALVE P&ID VLV VLV VLV VLV ACT NRM TST TST STR REL PROC NUMBER DESCRIPTION C'OORD CLS CAT SIZ TYP TYP POS REQ FRQ TIM REQ NO. REMARKS SI-161 FI-927 ISOL OC 42-E 2 A 3/4 GL M LC LT j C V-651B 8801A CHG INJ TO RCS 43-D 2 B 4 GA E C Pi 2Y NA V-2J6 EF Q 100 V-3E9 8801B CHG INJ TO RCS 43-C 2 B 4 GA E C Pi 2Y NA V-2J6 EF Q 100 V-3E9 8802A SI PP-I DISCH ISOL OC 54-E 2 A 4 GA E LC PI 2Y NA V-2J6 LT R* -c V-7E *Per Tech Spec EF CS 20o CS14 V-3LI 8802B SI PP-2 DISCH ISOL OC 54-D 2 A 4 GA E LC PI 2Y NA V-2J6 LT R* c V-7E *Per Tech Spec EF CS 20o CS14 V-3LI 8803A CHG INJ TO RCS 45-C 2 B 4 GA E C Pi 2Y NA V-2C EF Q 100 V-3EI I 8803B CHG INJ TO RCS 45-B 2 B 4 GA E C P1 2Y NA V-2C EF Q 100 V-3E11 I 8804A CHG PP SUCT FROM RHR- 48-B 2 B 8 GA E C Pi 2Y NA V-2VI EF R 20o R03 V-3116 8804B S1 PP SUCT FROM RHR 58-C 2 B 8 GA E C Pi 2Y NA V-2V I EF R 20o R03 V-3L16 8805A RWST TO CHG PP SUCT 48-C 2 B 8 GA E C Pi 2Y NA V-2Z EF CS 1lo CS26 V-3KI I 10006620.1ST 40MIS 38

C PACIFIC GAS & ELECTRIC COMPANY DIABLO CANYON POWER PLANT - UNITS I & 2

• INSERVICE TESTING PROGRAM PLAN - VALVES TABLE 2.0 REV 20 (2003)

ASME/ANSI OM-1987 (INCLUDING OMa-1988 ADDENDA) PAGE 23 OF 52 SAFETY INJECTION SYSTEM P& ID NO. 1020 09 VALVE VALVE P & ID VLV VLV VLV VLV ACT NRM TST TST STR REL PROC NUMBER DESCRIPTION COORD CLS CAT SIZ TYP TYP POS REQ FRQ TIM REQ NO. REMARKS 8805B RWST TO CHARG PP SUCT 48-C 2 B 8 GA E C Pl 2Y NA V-2Z EF CS lo CS26 V-3Kl1 8807A SI PPI SUC TO CCP SUC XTIE 48-B 2 B 4 GA E C Pl 2Y NA V-2H EF Q 20o V-3L3 8807B SI PPI SUC TO CCP SUC XTIE 48-B 2 B 4 GA E C Pl 2Y NA V-2H EF Q 20o V-3L3 8808A ACCUM-1 DISCH ISOL 31-D 2 B 10 GA E LO Pl 2Y NA V-2PI EF CS 30o CS33 V-3L4 8808 ACCUM-2 DISCH ISOL 33-D 2 B 10 GA E LO Pl 2Y NA V-2PI EF 'CS 30o CS33 V-3L4 8808C ACCUM-3 DISCH ISOL 35-D 2 B 10 GA E LO Pl 2Y NA V-2PI EF CS 30o CS33 V-3L4 8808D ACCUM-4 DISCH ISOL 37-D 2 B 10 GA E LO Pl 2Y NA V-2PI EF CS 30o CS33 V-3L4 8809A RHR TO CLD LEGS-1&2 ISOL OC 54-C 2 B 8 GA E LO Pl 2Y NA V-2J3 EF CS 20c CS15 V-3L5 8809B RHR TO CLD LEGS-3&4 ISOL OC 54-B 2 B 8 GA E LO Pl 2Y NA V-2J3 EF CS 20c CS15 V-3L5 8818A RHR TO COLD LEG- I CK 52-C I A,C 6 CK N C LT R* c V-5A2 *Per Tech Spec EN R 0 R013 V-1813 8818B RHR TO COLD LEG-2 CK 52-B I A,C 6 CK N C LT R* c V-5A2 *Per Tech Spec EN R o R013 V-18H 10006620.1ST 40MIS 39

C C PACIFIC GAS & ELECTRIC COMPANY DIABLO CANYON POWER PLANT - UNITS I & 2 INSERVICE TESTING PROGRAM PLAN - VALVES TABLE 2.0 REV 20 (2003)

ASMEIANSI OM-1987 (INCLUDING OMa-1988 ADDENDA) PAGE 24 OF 52 SAFETY INJECTION SYSTEM P& ID NO. 1020 09 VALVE VALVE P & ID VLV VLV VLV VLV ACT NRM TST TST STR REL PROC NUMBER DESCRIPTION COORD CLS CAT SIZ TYP TYP POS REQ FRQ TIM REQ NO. REMARKS 8818C RHRTO COLD LEG-3 CK 52-B 1 A,C 6 CK N C LT c V-5A2 *Per Tech Spec EN RR 0 R013 V-18B 8818D RHR TO COLD LEG-4 CK 52-A I A,C. 6 CK N C LT c V-5A2 *PerTech Spec EN R 0 RO13 V-18B 8819A Si TO COLD LEG-I CK 52-C I A,C 2 CK N C LT c V-SAI *PerTech Spec EC R 0 R04 V-15 8819B Si TO COLD LEG-2 CK 52-B I A,C *2 CK N C LT R c V-5AI *PerTech Spec EC 0 R04 V-15 8819C Si TO COLD LEG-3 CK 50-B I A,C 2 CK N C LT C V-5AI *Per Tech Spec EC R*

R* 0 R04 V-15 8819D Si TO COLD LEG-4 CK 50-A A,C 2 CK N C LT R C V-5A1 *PerTech Spec I EC R*

0 R04 V-15 8820 CHG INJ 2ND OFF CK 41-D C 3 CK N C EP CRS R09 V-4B 2 EC 0

0 R09 V-15 I 8821A Si PP-I DISCH ISOL 55-E B 4 GA E 0 Pl 2Y NA V-2J6 2 EF Q 20c V-3L2A 8821 B SI PP-2 DISCH ISOL 55-D B 4 GA E 0 Pl 2Y Q NA V-2J6 EF 20c V-3L2B 8835 SI COLD INJECT ISOL OC 54-C 2 B 4 GA E LO P1 2Y NA V-2J6 EF CS 20c CS16 V-31L6 10006620.1ST 40MIS 40

C C C PACIFIC GAS & ELECTRIC COMPANY DIABLO CANYON POWER PLANT - UNITS 1 & 2 INSERVICE TESTING PROGRAM PLAN - VALVES TABLE 2.0 REV 20 (2003)

ASME/ANSI OM-1987 (INCLUDING OMa-1988 ADDENDA) PAGE 25 OF 52 SAFETY INJECTION SYSTEM P& ID NO. 1020 09 VALVE VALVE P & ID VLV VLV VLV VLV ACT NRM TST TST STR REL PROC NUMBER DESCRIPTION COORD CLS CAT SIZ TYP TYP POS REQ FRQ TIM REQ NO. REMARKS 8871 Si TEST LINE ISOL IC 38-C 2 A 3/4 GL A C PI 2Y NA V-201 LT 3 c V-651B EF Q 10c V-3S5 8875A St ACCUM I NIT FILL & VENT 171-E 2 B I GL A C PI 2Y NA V-2P2 8875B Si ACCUM 2 NIT FILL & VENT 173-E 2 B I GL A C PI 2Y NA V-2P2 8875C Si ACCUM 3 NIT FILL & VENT 175-E 2 B I GL A C PI 2Y NA V-2P2 8875D Si ACCUM 4 NIT FILL & VENT 177-E 2 B I GL A C PI 2V NA V-2P2 8876A Si ACCUM I DRAIN 170-D 2 B I GL A C PI 2Y NA V-2P2 8876B SI ACCUM 2 DRAIN 172-D 2 B I GL A C PI 2Y NA V-2r2 8876C Si ACCUM 3 DRAIN 174-D 2 B I GL A C PI 2Y NA V-2P2 8876D SI ACCUM 4 DRAIN 177-D 2 B I GL A C PI 2Y NA v-2P2 V

8880 N2 SUP TO ACCUM ISOL OC 39-E 2 A I GL A 0 PI 2Y NA V-2J7 LT J c V-6S1 A

EF Q 1Oc V-3S5 8883 SI PP-I TO TST LINE ISO OC 54-E 2 A 3/4 GL A C PI 2Y NA V-2J7 LT J c V-6511B EF Q 1Oc V-3S5 8900A CHG INJ LOOP- I CK 40-E I C 1.5 CK N C EC R o R09 V-15 8900B CHG INJ LOOP-2 CK 40-B I C 1.5 CK N C EC R o R09 V-15 8900C CHG INJ LOOP-3 CK 40-C I C 1.5 CK N C EC R o R09 V-15 8900D CHG INJ LOOP-4 CK 40-D I C 1.5 CK N C EC R o R09 V-15 10006620.1ST 40MIS 41

C C C PACIFIC GAS & ELECTRIC COMPANY DIABLO CANYON POWER PLANT - UNITS I & 2 INSERVICE TESTING PROGRAM PLAN - VALVES TABLE 2.0 REV 20 (2003)

ASME/ANSI OM- 1987 (INCLUDING OMa- 1988 ADDENDA) PAGE 26 OF 52 SAFETY INJECTION SYSTEM P& ID NO. 1020 09 VALVE VALVE P & ID VLV VLV VLV VLV ACT NRM TST TST STR REL PROC NUMBER DESCRIPTION COORD CLS CAT SIZ TYP TYP POS REQ FRQ TIM REQ NO. REMARKS 8905A SI TO HOT LEG-I CK 52-E I A,C 2 CK N C EC R o R04 V-15 LT R* c V-5C *Per Tech Spec 8905B SI TO HOT LEG-2 CK 52-E I A,C 2 CK N C EC R o R04 V-15 LT R c V-SC *Per Tech Spec 8905C SI TO HOT LEG-3 CK 52-D I A,C 2 CK N C EC R o R04 V-15 LT R c V-5C *Per Tech Spec 8905D SI TO HOT LEG-4 CK 52-D I A,C 2 CK N C EC R o R04 V-15 LT R c V-5C *Per Tech Spec 8916 N2 SUP TO ACCUM CK IC 38-E 2 A,C I CK N C LT R c V-651A EC R c RR2 V-651 A 8919A SI PP-I TO RWST CK 57-E 2 C 3/4 CK N C EC Q o P-SIP 8919B SI PP-2 TO RWST CK 57-D 2 C 3/4 CK N C EC Q o P-SIP 8922A SI PP-I DISCH CK 56-E 2 C 4 CK N C EC R o RO5 V-15 EC Q c P-SIP 8922B SI PP-2 DISCH CK 56-D 2 C 4 CK N C EC R o RO5 V-15 EC Q C P-SIP 8923A SI PP-I SUCT 58-E 2 B 6 GA E O PI. 2Y NA V-2H EF Q 30c V-3LIOA 8923B SI PP-2 SUCT 58-D 2 B 6 GA E O PI 2Y NA V-211 EF Q 30c V-3LIOB 8924 RWST TO CHG PP CK 48-C 2 C 8 CK N C EP CS o V-3K10 EC R o R020 V-15 EC R c R020 M-86G 10006620.1ST 40MIS 42

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COMPANY MlARI nrANVW PfAWFR PI ANT.. IINl I l7 INSERVICE TESTING PROGRAM PLAN - VALVES TABLE 2.0 REV 20 (2003)

ASME/ANSI OM-1987 (INCLUDING OMa-1988 ADDENDA) PAGE 27 OF 52 SAFETY INJECTION SYSTEM P& ID NO. 1020 09 VALVE VALVE P & ID VLV VLV VLV VLV ACT NRM TST TST STR REL PROC NUMBER DESCRIPTION COORD CLS CAT SIZ TYP TYP POS REQ FRQ TIM REQ NO. REMARKS 8948A LOOP-I COLD INJ CK 30-B I A,C 10 CK N C LT R* C V-5A2 Per Tech Spec EN RR 0 RR4 V-18A 8948B LOOP-2 COLD INJ CK 30-D I A,C 10 CK N C LT RR c V-5A2 *Per Tech Spec EN RR 0 RR4 V-18A 8948C LOOP-3 COLD INJ CK 30-A I A,C 10 CK N C LT R c V-5A2 *Per Tech Spec EN RR 0 RR4 V-18A 8948D LOOP-4 COLD INJ CK 30-A I A,C 10 CK N C LT R* c V-5A2 'Per Tech Spec EN RR 0 RR4 V-18A 8949A Si TO HOT LEG- I CK 50-E I A,C 6 CK N C EC R 0 R06 V-15 LT RR C V-5C *Per Tech Spec 8949B SI TO HOT LEG-2 CK 50-E I A,C 6 CK N C EC R 0 R06 V-15 LT R* C V-5C *Per Tech Spec 8949C Si TO HOT LEG-3 CK 50-D I A,C 6 CK N C EC R 0 R06 V-15 LT R C V-5C *Per Tech Spec 8949D SI TO HOT LEG-4 CK 50-D I A,C 6 CK N C EC R 0 R06 V-15 LT R* C V-5C Per Tech Spec 8956A ACCUM-1 DISCH CK 31-C I A,C 10 CK N C LT R C V-5A I *Per Tech Spec EN RR 0 RR5 V-18A 8956B ACCUM-2 DISCH CK 31-B I A,C 10 CK N C LT R C V-5AI *Per Tech Spec EN RR 0 RR5 V-18A 8956C ACCUM-3 DISCH CK 31-A I A,C 10 CK N C LT R* c V-5AI *Per Tech Spec EN RR 0 RR5 V-18A 8956D ACCUM-4 DISCH CK 31-A I A,C 10 CK N C LT R c _ _

V-5AI *Per Tech Spec EN RR o RR5 V- ISA 10006620.1ST 40MIS 43

C C PACIFIC GAS & ELECTRIC COMPANY DIABLO CANYON POWER PLANT - UNITS 1 & 2 INSERVICE TESTING PROGRAM PLAN - VALVES TABLE 2.0 REV 20 (2003)

ASME/ANSI OM-1987 (INCLUDING OMa-1988 ADDENDA) PAGE 28 OF 52 SAFETY INJECTION SYSTEM P& ID NO. 1020 09 VALVE VALVE P & ID VLV VLV VLV VLV ACT NRM TST TST STR REL PROC NUMBER DESCRIPTION COORD CLS CAT SIZ TYP TYP POS REQ FRQ TIM REQ NO. REMARKS 8961 Si TEST LINE ISOL OC 39-C 2 A 3/4 GL A C Pi 2Y NA V-2J7 LT J c V-651B EF Q 10c V-3S5 8974A Si RECIRC TO RWST 57-D IWV. B 2 GL E LO Pi 2Y NA V-2V2 EF CS 10c CS17 V-3L15 8974B SI RECIRC TO RWST 57-D 2 B 2 GL E LO Pi 2Y NA V-2V2 EF LS 1Oc CS17 V-3L15 8976 RWST TO Si PP ISOL 59-D 2 B 8 GA E LO PI 2Y NA V-2J6 EF CS 20c CS18 V-3L13 8977 RWST TO Si PP CK 59-D 2 C 8 CK N C EP Q o P-SIP EC R o R019 V-15 EC R c ROI9 M-86AI 8980 RWST TO RHR PPS ISOL OC 59-B 2 B 12 GA E LO Pi 2Y NA V-2J3 EF CS 25c CS19 V-3L14 8981 RWST TO RHR rP CK 59-B 2 C 12 CK N C EC R o R07 V-4C EC CS c CS34 V-4D 8982A CONT RCRC SMP TO RHRPI ISO 52-A 2 B 14 GA E LC Pi 2Y NA V-206 EF R 25o RO8 V-3L17 8982B CONT RCRC SMP TO RHRP2 ISO 53-A 2 B 14 GA E LC Pi 2Y NA V-206 EF R 25o RO8 V-3L17 RV-8851 SI TO CL RELIEF TO PRT 55-D 2 C 3/4 RV N C RT T o M-77 1750ff RV-8853A Si PPI DISCH TO PRT RV 55-E 2 C 3/4xl RV N C RT T o M-77 1750tf RV-8853B Si PP2 DISCH TO PRT RV 54-D 2 C 3/4xl RV N C RT T o M-77 1750#

RV-8855A ACCUM I PRES RV 31-E 2 C I RV N C RT T o M-77 7000 RV-8855B ACCUM 2 PRES RV 34-E 2 C I RV N C RT T o M-77 7000f RV-8855C ACCUM 3 PRES RV 36-E 2 C 1 RV N C RT T o M-77 700#f 10006620.1ST. 40MIS 44

(7 C PACIFIC GAS & ELECTRIC COMPANY DIABLO CANYON POWER PLANT - UNITS I & 2 INSERVICE TESTING PROGRAM PLAN - VALVES TABLE 2.0 REV 20 (2003)

ASME/ANSI OM-1987 (INCLUDING OMa-1988 ADDENDA) PAGE 29 OF 52 SAFETY INJECTION SYSTEM P& ID NO. 1020 09 VALVE VALVE P & ID VLV VLV VLV VLV ACT NRM TST TST STR REL PROC NUMBER DESCRIPTION COORD CLS CAT SIZ TYP TYP POS REQ FRQ TIM REQ NO. REMARKS RV-8855D ACCUM 4 PRES RV 38-E 2 C' I RV N C RT T 0 M-77 700#

RV-8856A' RHR PPI DISCH TO PRT RV 54-B 2 C 2X3 RV N C RT T 0 M-77 60011 RV-8856B RHR PP2 DISCH TO PRT RV 54-B 2 C 2X3 RV N C RT T 0 M-77 60011 RV-8858 RWST TO Si PP SUCT RV 58-D 2 C 3/4 RV N C RT T 0 M-77 220#

10006620.1ST 40MIS 45

C r PACIFIC GAS & ELECTRIC COMPANY DIABLO CANYON POWER PLANT - UNITS I & 2 INSERVICE TESTING PROGRAM PLAN - VALVES TABLE 2.0 REV 20 (2003)

ASME/ANSI OM-1987 (INCLUDING OMa-1988 ADDENDA) PAGE 30 OF 52 RESIDUAL HEAT REMOVAL SYSTEM P& ID NO. 1020 10 VALVE VALVE P & ID VLV VLV VLV VLV ACT NRM TST TST STR REL PROC NUMBER DESCRIPTION COORD CLS CAT SIZ TYP TYP POS REQ FRQ TIM REQ NO. REMARKS FCV-641A RHRI PP-I RECIRC 34-E 2 B 2 GL E C PI 2Y NA V-2D EF Q loo/c V-3MIA FCV-641 B RHR PP-2 RECIRC 34-B 2 B 2 GL E C PI 2Y NA V-2D EF Q 1oo/c V-3MIB HCV-637 RHR HX-2 OUTLET 31-B. 2 B 8 BA A 0 EF Q 30o V-3M2B PI 2Y NA V-2J3 HCV-638 RHR HX-2 OUTLET 31-D 2 B 8 BA A 0 EF Q 30o V-3M2A PI 2Y NA V-2J3 8700A RHR PP-I SUCT OC 37-D 2 B 14 GA E 0 PI 2Y NA V-2D2 EF Q 120c V-3M4A 8700B RHR PP-2 SUCT OC 37-B 2 B 14 GA E 0 PI 2Y NA V-2D2 EF Q 120c V-3M4B 8701 RCS LOOP-4 TO RR IC 38-D I A 14 GA E LC PI 2Y NA V-2D3 LT R* c V-7C *Per Tech Spec EF CS 160o/c CS31 V-3M5 8702 RCS LOOP-4 TO RHR 39-D I A 14 GA E LC PI 2Y NA V-2D3 LT R* c V-7C *Per Tech Spec EF CS 160o/c CS31 V-3M5 8703 RHR TO HOT LEGS-I, 2 IC 38-B 2 A 12 GA E LC PI 2Y NA V-2M3 EF CS 85o CS20 V-3M6 LT R* c V-SC *PerTech Spec 10006620.1ST 40MIS 46

(' C PACIFIC GAS & ELECTRIC COMPANY DIABLO CANYON POWER PLANT - UNITS I & 2 INSERVICE TESTING PROGRAM PLAN - VALVES TABLE 2.0 REV 20 (2003)

ASME/ANSI OM-1987 (INCLUDING OMa-1988 ADDENDA) PAGE 31 OF 52 RESIDUAL HEAT REMOVAL SYSTEM P& ID NO. 1020 10 VALVE VALVE P&ID VLV VLV VLV VLV ACT NRM TST TST STR REL PROC NUMBER DESCRIPTION COORD CLS CAT SIZ TYP TYP POS REQ FRQ TIM REQ NO. REMARKS 8716A RHR TRAIN XTIEOC 30-D 2 B 8 GA E OPl 2Y NA V-2J3 EF Cs 200/c CS27 V-3M7 8716B RHR TRAIN XTIE OC 30-C 2 B 8 GA E OPi 2Y NA V-2J3 EF CS 200/c CS27 V-3M7 8730A RHR PP-I DISCH CK 35-D 2 C 8 CK N C EP Q 0 P-RHR EC CS 0 CS21 V-4B I 8730B RHR PP-2 DISCH CK 35-C 2 C 8 CK N C EP Q 0 P-RHR EC CS 0 CS21 V-4B 8740A RHR TO HOT LEG-I CK 39-B A/C 8 CK N C EN R 0 RO12 V-18C I LT R* c V-SC *Per Tech Spec 8740B RHR TO HOT LEG-2 CK 39-A A/C 8 CK N CEN 'R 0 RO12 V-18C -

LT R* c V-5C *Per Tech Spec 8742A RHR HT EX-I DISCH CK 32-D 2 C 8 CK N C EC CS 0 CS28 V4B I EC Q c P-RHR 8742B RHR HT EX-2 DISCH CK 32-B 2 C .8 CK N C EC CS 0 CS28 V-4B3 I EC Q c P-RHR RV-8707 RHR PPS SUCT FROM HL4 RV 38-D 2 C 3x4 RV N C RT T 0 M-77 450#

RV-8708 RHR TO HL1&2 TO PRT RV 38-B 2 C 3/4xl RV N C RT T 0 M-77 600#

10006620.1ST 40MIS 47

C c PACIFIC GAS & ELECTRIC COMPANY DIABLO CANYON POWER PLANT - UNITS I & 2 INSERVICE TESTING PROGRAM PLAN - VALVES TABLE 2.0 REV 20 (2003)

ASME/ANSI OM-1987 (INCLUDING OMa-1988 ADDENDA) PAGE 32 OF 52 NUCLEAR STEAM SUPPLY SAMPLING SYSTEM P& ID NO. 1020 11 VALVE VALVE P & ID VLV VLV VLV VLV ACT NRM TST TST STR REL PROC NUMBER DESCRIPTION COORD CLS CAT SIZ TYP TYP POS REQ FRQ TIM REQ NO. REMARKS 9354A PZR STM SAMPLE ISOL IC . 21-A 2 A 3/8 GL A 0 Pi 2Y NA V-203 LT J c V-676A EF Q 1oc V-3SI 9354B PZR STM SAMPLE ISOL OC 22-A 2 A 3/8 GL A 0 Pi 2Y NA V-2J I LT J c V-676A EF Q 1Oc V-3SI 9355A PZR LIQUID SAMPLE ISOL IC 21-B 2 A 3/8 GL A 0 Pi 2Y NA V-203 LT J c V-659A EF Q 10c V-3SI 9355B PZR LIQUID SAMPLE ISOL OC 22-B 2 A 3/8 GL A 0 Pi 2Y NA V-2J I LT J c V-659A EF Q 1Oc V-3SI 9356A HOT LEG SAMPLE ISOL IC 21-B 2 A 3/8 GL A 0 Pi 2Y NA V-203 LT J c V-659B EF Q 1oc V-3S I 10006620.1ST 40MIS 48

C C C PACIFIC GAS & ELECTRIC COMPANY DIABLO CANYON POWER PLANT - UNITS I & 2 INSERVICE TESTING PROGRAM PLAN - VALVES TABLE 2.0 REV 20 (2003)

ASME/ANSI OM-1987 (INCLUDING OMa-1988 ADDENDA) PAGE 33 OF 52 NUCLEAR STEAM SUPPLY SAMPLING SYSTEM P& ID NO. 1020 11 VALVE VALVE P & ID VLV VLV VLV VLV ACT NRM TST TST STR REL PROC NUMBER DESCRIPTION COORD CLS CAT SIZ TYP TYP POS REQ FRQ TIM REQ NO. REMARKS 9356B HOT'LEG SAMPLE ISOL OC 22-B 2 A 3/8 GL A 0 Pi 2Y NA V-2J I LT J c V-659B EF Q loc V-3St 9357A ACCUM SAMPLE ISOL IC 21-C 2 A 3/8 GI A 0 Pi 2Y NA V-203 LT 3 c V-659C EF Q 1Oc V-3SI 9357B ACCUM SAMPLE ISOL OC 22-C 2 A 3/8 GI A 0 Pi 2Y NA V-2J I LT J c V-659C EF Q 1oc V-3SI 10006620.1ST 40MIS 49

(7 C PACIFIC GAS & ELECTRIC COMPANY DIABLO CANYON POWER PLANT - UNITS I & 2 INSERVICE TESTING PROGRAM PLAN - VALVES TABLE 2.0 REV 20 (2003)

ASME/ANSI OM-1987 (INCLUDING OMa-1988 ADDENDA) PAGE 34 OF 52 CONTAINMENT SPRAY SYSTEM P& ID NO. 1020 12 VALVE VALVE P & ID VLV VLV VLV VLV ACT NRM TST TST STR REL PROC NUMBER DESCRIPTION COORD CLS CAT SIZ TYP TYP POS REQ FRQ TIM REQ NO. REMARKS CS-31 CS PP-I TO MEDT ISOL OC 33-D 2 A .75 GL M LC LT J c V-631 PASSIVE CS-32 CS PP-2 TO MEDT IOL OC 33-A 2 A .75 GL M LC LT C V-630 PASSIVE 8992 CS ADD TK STOP 37-B 2 B 3 GA E LO Pi 2Y NA V-2G PASSIVE 8994A NaOH CS EDUCTOR ISOL 36-B 2 B 3 GA E C P1 2Y NA V-2G EF CS 100 CS22 V-312 8994B NaOH CS EDUCTOR ISOL 37-B 2 B 3 GA E C Pi 2Y NA V-2G EF CS 1oo CS22 V-312 8998A CS ADD TK OUT CK 35-C 2 AC 3 CK N C EC CS 0 CS23 V-31 1 LT 2Y c V-21 8998B CS ADD TK OUT CK 35-B 2 A,C 3 CK N. C EC CS 0 CS23 V-311 LT 2Y c V-21 9001 A CS PP-I ISOL 34-D 2 A 8 GA E C Pi 2Y NA V-2B LT i c V-63 1 EF Q 100 V-313A 900113 CS PP-2 ISOL 34-A 2 A 8 GA E C Pi 2Y NA V-2B LT J c V-630 EF Q Io V-313B 10006620.1ST 40MIS 50

(7 C' PACIFIC GAS & ELECTRIC COMPANY DIABLO CANYON POWER PLANT - UNITS I & 2 INSERVICE TESTING PROGRAM PLAN - VALVES TABLE 2.0 REV 20 (2003)

ASME/ANSI OM-1987 (INCLUDING OMa-1988 ADDENDA) PAGE 35 OF 52 CONTAINMENT SPRAY SYSTEM P& ID NO. 1020 12 VALVE VALVE P & ID VLV VLV VLV VLV ACT NRM TST TST STR REL PROC NUMBER DESCRIPTION COORD CLS CAT SIZ TYP TYP POS REQ FRQ TIM REQ NO. REMARKS 9002A CS PP-I DISCH CK 33-D 2 C 8 CK N C EN RR o/c RRIO V-17 9002B CS PP-2 DISCH CK 33-A 2 C 8 CK N C EN RR o/c RRI0 V-17 9003A RHR HX-I TO CS-A HDR 33-D 2 B 8 GA E C Pi 2Y NA V-2B2 EF R 15o R03 V-314 9003B RHR HX-2 TO CS-B HDR 33-B 2 B 8 GA E C PI 2Y NA V-2B2 EF R 150 R03 V-314 901 IA CS HDR-A ISOL CK IC 31-D 2 A,C 8 CK N C LT R c V-631 EM RR o/c RR8 V-18 901 IB CS HDR-B ISOL CK IC 31-A 2 A,C 8 CK N C LT R c V-630 EM RR o/c RR8 V-18 RV-930 CS ADD TK I VAC BREAK 37-C 2 C 1.5 RV N C RT T 0 M-77 -1.5# vac RV-931 CS ADD TK2'VAC BREAK 37-C 2 C 1.5 RV N C RT T 0 M-77 -1.5# vac RV-8987 CS ADD TK1 TO AUX BLDG SMP 38-C 2 C 3/4xl RV N C RT T 0 M-77 I0#

RV-9007A CS HDR A OC RV 32-D 2 C 3/4 RV N C RT T 0 M-77 260#

RV-9007B CS HDR B OC RV 32-B 2 C 3/4 RV N C RT T 0 M-77 260#

10006620.1ST 40MIS 51

(7 C

DAPfltdItF AJ& LfTFl Pi I S rrnKA PAMV C'

DARI CANVON POWFR PIANT - INITSI 1 7 INSERVICE TESTING PROGRAM PLAN - VALVES TABLE 2.0 REV 20 (2003)

ASME/ANSI OM-1987 (INCLUDING OMa-1988 ADDENDA) PAGE 36 OF 52 COMPONENT COOLING WATER SYSTEM P& ID NO. 1020 14 VALVE VALVE P & ID VLV VLV VLV VLV ACT NRM TST TST STR REL PROC NUMBER DESCRIPTION COORD CLS CAT SIZ TYP TYP POS REQ FRQ TIM REQ NO. REMARKS CCW-4 SUCT X-TIE VLV (50-C) 3 B 20 BV M LO EF R N/A RO16 V-3H15 BETWEEN HDRS B&C EP Q N/A V-3H 14 CCW-5 SUCT X-TIE VLV (52-C) 3 B 20 BV M LO EF R N/A RO16 V-3H15 BETWEEN HDRS A&C EP Q N/A V-3H14 CCW-16 CCW PP 2 DISCH (53-D) 3 B 20 BV M LO EF Q N/A P-CCW TO HEADER B CCW-17 CCW PP 3 DISCH (55-D) 3 B 20 BV M LO EF Q N/A P-CCW TO HEADER B CCW-18 CCW PP I DISCH (51-E) 3 B 20 BV M LO EF Q N/A P-CCW TO HEADER A CCW-19 CCW PP 2 DISCH (53-E) 3 B 20 BV M LO EF Q N/A P-CCW TO HEADER A CCW-23 CCW HEADER A TO C (58-E) 3 B 24 BV M LO EF Q N/A P-CCW ISOLATION VALVE CCW-24 CCW HEADER B TO C (58-D) 3 B 24 BV M LO EF Q N/A P-CCW ISOLATION VALVE 10006620.1ST 40MIS 52

C C PACIFIC GAS & ELECTRIC COMPANY DIABLO CANYON POWER PLANT - UNITS I & 2 INSERVICE TESTING PROGRAM PLAN - VALVES TABLE 2.0 REV 20 (2003)

ASME/ANSI OM-1987 (INCLUDING OMa-1988 ADDENDA) PAGE 37 OF 52 COMPONENT COOLING WATER SYSTEM P& ID NO. 1020 14 VALVE VALVE P & ID VLV VLV VLV VLV ACT NRM TST TST STR REL PROC NUMBER DESCRIPTION COORD CLS CAT SIZ TYP TYP POS REQ FRQ TIM REQ NO. REMARKS CCW-581 CCW FCV-749 BYPASS CK IC 71-B 2 A,C 3/4 CK N C LT R c V-620 EC R 0 RO15 V-620 RV function EC R c RO15 V-620 CCW-585 CCW TO RCP & RX VSL 72-E 2 A,C 10 CK N 0 LT R c V-619 SUPPORT CK IC EC R C RR2 V-619 CCW-601 CCW PP-I HDR-A CK 52-E 3 C 20 CK N O- EC Q o/c P-CCW CCW-602 CCW PP-2 HDR-A CK 53-E 3 C 20 CK N 0 EC Q o/c P-CCW CCW-603 CCW PP-3 HDR-A CK 55-E 3 C 20 CK N 0 EC Q o/c P-CCW CCW-607 CCW PP-I HDR-B CK 52-D 3 C 20 CK N 0 EC Q o/c P-CCW CCW-608 CCW PP-2 HDR-B CK 53-D 3 C 20 CK N 0 EC Q 0/c P-CCW CCW-609 CCW PP-3 HDR-B CK 55-D 3 C 20 CK N 0 EC Q o/c P-CCW CCW-670 CCW FCV-750 BYPASS CK IC 73-B 2 A,C 3/4 CK N C LT R c V-621 EC R 0 RO15 V-621 RV function EC R c RO15 V-621 CCW-695 CCW TO EXCS LTDN HX CK OC 98-D 2 A,C 4 CK N 0 LT R c V-623 EC R c RR2 V-623 FCV-355 CCW HDR-C ISOL 59-D 3 B 20 BV E 0 Pi 2Y NA V-2F EF CS 20c CS24 V-3113 FCV-356 CCW TO RCP & RX VSL 72-E 2 A 10 BV E 0 PI 2Y NA V-2J2 SUPPORT ISOL OC LT J c V-619 EF CS 25c CS24 V-3114 FCV-357 RCP THM BAR CCW RTN ISO OC 73-B 2 A 6 GL E 0 Pi 2Y NA V-2J2 LT J c V-621 EF CS 30c CS24 V-3115 10006620.1ST 40MIS 53

CI C c PACIFIC GAS & ELECTRIC COMPANY DIABLO CANYON POWER PLANT - UNITS I & 2 INSERVICE TESTING PROGRAM PLAN - VALVES TABLE 2.0 REV 20 (2003)

ASME/ANSI OM-1987 (INCLUDING OMa-1988 ADDENDA) PAGE 38 OF 52 COMPONENT COOLING WATER SYSTEM P& ID NO. 1020 14 VALVE VALVE P & ID VLV VLV VLV VLV ACT NRM TST TST STR REL PROC NUMBER DESCRIPTION COORD CLS CAT SIZ TYP TYP POS REQ FRQ TIM REQ NO. REMARKS FCV-361 CCWFRM XCS LTDN HX ISO OC 98-B 2 A 4 BV A C Pi 2Y NA V-2J2 LT i c V-623 EF Q lOc V-3S6 FCV-363 RCPS CLR CCW RTN ISOL OC 72-B 2 A 6 BV E 0 Pi 2Y NA V-212 LT J c V-620 EF CS 25c CS24 V-31H6 FCV-364 RHR HX-2 CCW RETURN 60-C 3 B 12 BV A C Pi 2Y NA V-211 EF Q 1o V-31-17 FCV-365 RHR HX- I CCW RETURN 104-C 3 B 12 BV A C Pi 2Y NA V-211 EF Q Io V-3H7 FCV-430 CCW HX-I OUT ISOL 58-E 3 B 30 BV E 0 PI 2Y NA V-2F EF Q 30o V-3H8 FCV-431 CCW HX-2 OUT ISOL 58-D 3 B 30 BV E 0 Pi 2Y NA V-2F EF Q 30o V-31-18 FCV-749 RCPS CLR CCW RTN ISOL IC 72-B 2 A 6 BV E 0 PI 2Y NA V-202 LT J c V-620.

EF CS 20c CS24 V-3H10 FCV-750 RCP THM BAR CCW RTN ISO IC 73-B 2 A 6 GL E 0 Pi 2Y NA V-202 LT J c V-621 EF CS 30c CS24 V-3119 LCV-69 MU WTR TO CCW HDR-A 55-B 3 B 3 GL A C EF Q 20o V-31111 LCV-70 MU WTR TO CCW HDR-B 55-B 3 B 3 GL A C EF Q 20o V-3111 I RCV-16 CCW SURGE TK VENT 56-C 3 B 3 BA A 0 Pi 2Y NA V-21:

EF Q I oc V-31112 10006620.1ST 40MIS 54

C C' PACIFIC GAS & ELECTRIC COMPANY DIABLO CANYON POWER PLANT - UNITS I & 2 INSERVICE TESTING PROGRAM PLAN - VALVES TABLE 2.0 REV 20 (2003)

ASME/ANSI OM-1987 (INCLUDING OMa-1988 ADDENDA) PAGE 39 OF 52 COMPONENT COOLING WATER SYSTEM P& ID NO. 1020 14 VALVE VALVE P & ID VLV VLV VLV VLV ACT NRM TST TST STR REL PROC NUMBER DESCRIPTION COORD CLS CAT SIZ TYP TYP POS REQ FRQ TIM REQ NO. REMARKS RV-41 RCP3 THRML BARRIER CCW RTN 72-D 3 C 3/4xl RV N C RT T 0 M-77 2335#

RV-42 RCP4 THRML BARRIER CCW RTN 73-D 3 C 3/4xl RV N C RT T 0 M-77 2335#

RV-43 RCP2 THRML BARRIER CCW RTN 70-D 3 C 3/4x I RV N C RT T 0 M-77 2335#

RV-44 RCPI THRML BARRIER CCW RTN 74-D 3 C 3/4xl RV N C RT T 0 M-77 2335#

RV-45 CCW SURGE TANK RV 57-C 3 C 3x4 RV N C RT T 0 M-77 30#

RV-46 FCV-365 BYPASS RV 103-C 3 C 3/4xl RV N C RT T 0 M-77 70 RV47 CCW RTN FROM RHR HX2 RV 61-C 3 C 3/4xl RV N C RT T 0 M-77 70ff RV-51 RCPS LO CLG RTN TO CCW RV 72-C 3 C 3 RV N C RT T 0 M-77 150#

RV-52 CCW RTN XCES LTDN HX RV 98-C 2 C 3 RV N C RT T 0 M-77 150#f 10006620.1ST 40MIS 55

( f PACIFIC GAS & ELECTRIC COMPANY DIABLO CANYON POWER PLANT - UNITS I & 2 INSERVICE TESTING PROGRAM PLAN - VALVES TABLE 2.0 REV 20 (2003)

ASME/ANSI OM-1987 (INCLUDING OMa-1988 ADDENDA) PAGE 40 OF 52 MAKEUP WATER SYSTEM P& ID NO. 1020 16 VALVE VALVE P & ID VLV VLV VLV VLV ACT NRM TST TST STR REL PROC NUMBER DESCRIPTION COORD CLS CAT SIZ TYP TYP POS REQ FRQ TIM REQ NO. REMARKS MU-963 AFW PP RECIRC TO CST CK 71-C 3 C 2 CK N C EC Q o P-AFW (78-C)

MU-965 CST TO MU H20 XFR PPS CK 70-E 3 C 4 CK N C EC Q o V-3U2 (78-E)

MU-968 MU H20 XFR PP-01 DISCH CK 74-D 3 C 4 CK N C EC Q 0 V-3U2 MU-970 MU H20 XFR PP-02 DISCH CK 75-D 3 C 4 CK N C EC 0 V-3U2 MU-971 MU H20 TO MISC SOURCES CK 71-E 3 C 4 CK N C EC Q, .0 V-3U2 (78-E)

MU-1555 CST H20 MIXING PP DISCH CK 71-C 3 C 3 CK N 0 EC Q c V-3UI (78-D)

MU-966 MU WATER PP RECIRC CK 73-D 3 C 4 CK N 0 EC Q 0 P-MUW MU-969 MU WATER PP RECIRC CK 75-D 3 C 4 CK N 0 EC Q 0 P-MUW 10006620.1ST 40MIS 56

C C C PACIFIC GAS & ELECTRIC COMPANY DIABLO CANYON POWER PLANT - UNITS I & 2 INSERVICE TESTING PROGRAM PLAN - VALVES TABLE 2.0 REV 20 (2003)

ASME/ANSI OM-1987 (INCLUDING OMa-1988 ADDENDA) PAGE41 OF52 SALTWATER SYSTEM P& ID NO. 1020 17 VALVE VALVE P & ID VLV VLV VLV VLV ACT NRM TST TST STR REL PROC NUMBER DESCRIPTION C OORD CLS CAT SIZ TYP TYP POS REQ FRQ TIM REQ NO. REMARKS SW-34 AS*' PP-I DISCH VAC RELIEF i 12B-D 3 C 3 CK N C EC R o/c RO10 V-18M RV function C 8A-E)

SW-170 ASW PP-I DISCH VAC RELIEF i 32B-D 3 C 3 CK N C EC R o/c RO10 V-18M RV function C38A-E)

SW-200 ASW PP- I DISCH CK 34-C 3 C 24 CK N 0 EC Q o/c P-ASW SW-201 ASW PP-2 DISCH CK 34-C 3 C 24 .CK N 0 EC Q olc P-ASW SW-301 ASW PP-2 DISCH VAC RELIEF i 1IB-D 3 C 3 CK N C EC R o/c . RO10 V-18M RV function C37A-E)

SW-303 ASW PP-2 DISCH VAC RELIEF 31B-D 3 C 3 CK N C EC R O/c RO10 V-18M RV function 37A-E)

FCV-495 ASW PP-2 CROSS TIE 35-C 3 B 24 BV E,M 0 Pi 2Y NA V-2A I EF Q 30 o/c V-3FI Manual Closed FCV-496 ASW PP-I CROSS TIE 35-C 3 B' 24 BV E,M 0 PI 2Y NA V-2AI EF Q o/c V-3F2 Manual Closed FCV-601 ASW UNIT CROSS TIE 34-C 3 B 24 BV E C Pi 2Y NA V-2A2 EF Q 30 o/c V-3F3 FCV-602 CCW HX-I SW INLET 36-C 3 B 24 BV A 0 Pi 2Y NA V-2F I(35-C) EF Q 60o V-3F4 UNIT I (EF Q 120o V-3F4 UNIT 2)

FCV-603 CCW HX-2 SW INLET 35-B 3 B 24 BV A 0 Pi 2Y NA V-2F EF Q 60o V-3F5 UNIT I (EF Q 90o V-31:5 UNIT 2) 10006620.1ST 40MIS 57

(P (7 C PACIFIC GAS & ELECTRIC COMPANY DIABLO CANYON POWER PLANT - UNITS I & 2 INSERVICE TESTING PROGRAM PLAN - VALVES TABLE 2.0 REV 20 (2003)

ASMEtANSI OM-1987 (INCLUDING OMa-1988 ADDENDA) PAGE 42 OF 52 FIRE PROTECTION SYSTEM P& ID NO. 1020 18 VALVE VALVE P & ID VLV VLV VLV VLV ACT NRM TST TST STR REL PROC NUMBER DESCRIPTION COORD CLS CAT SIZ TYP TYP POS REQ FRQ TIM REQ NO. REMARKS FP- 180 CONT FIREWATER ISOL IC 73-B 2 A,C 4 CK N C LT J c V-679 (FP-867) (73-D)

FCV-633 CONT FIREWATER ISOL OC 72-B 2 A. 3 GL A 0 Pi 2Y NA V-2J7 (72-E) LT J NA V-679 EF Q 1oc V-3S4 FP-306 FIREWATER SUPPLY TO 37-C 3 B 8 BV M C EF Q* NA V-3P4 Per Tech Spec AUX FEED PPS FP-307 FIREWATER SUPPLY TO 37-C 3 B 8 BV M C EF Q* NA V-3P4 *Per Tech Spec AUX FEED PPS 10006620.1ST 40MIS 58

(C C' PACIFIC GAS & ELECTRIC COMPANY DIABLO CANYON POWER PLANT - UNITS I & 2 INSERVICE TESTING PROGRAM PLAN - VALVES TABLE 2.0 REV 20 (2003)

ASME/ANSI OM-1987 (INCLUDING OMa-1988 ADDENDA) PAGE 43 OF 52 LIQUID RADWASTE SYSTEM P& ID NO. 1020 19 VALVE VALVE P & ID VLV VLV VLV VLV ACT NRM TST TST STR REL PROC NUMBER DESCRIPTION COORD CLS CAT SIZ TYP TYP POS REQ FRQ TIM REQ NO. REMARKS u :n LW;-OU LZf ll 1rf% nr r I I-u1

, wrQ I a Ifr L t %

Or A 'I iIA U xi I' IT D . VClf V -CL" EC R c RR2 V-652D FCV-253 RCDT PP DISCH ISOL IC 38-A 2 A 2.5 BA A 0 Pi 2Y NA V-205 LT J c V-650 EF Q 1oc V-3S3 FCV-254 RCDT PP DISCH ISOL OC 39-A 2 A 2.5 BA A 0 PI 2Y NA V-2J5 LT J c V-650

.EF Q I0c V-3S3 FCV-255 RCDT VENT ISOL IC 38-B 2 A 3/4 BA A 0 Pi 2Y NA V-205 LT J c V-65 IC EF Q loc V-3S3 FCV-256 RCDT VENT ISOL OC 39-B 2 A 3/4 BA A 0 P1 2Y NA V-2J5 LT J c V-651C EF Q 1Oc V-3S3 FCV-257 RCDT GAS ANAL ISOL OC 39-B 2 A 1/2 BA A C Pi 2Y NA V-2J5 LT J c V-651D EF Q 10c V-3S3 10006620.1ST 40MIS 59

C C PACIFIC GAS & ELECT RIC COMPANY DIABLO CANYON POWER PLANT - UNITS I & 2 INSERVICE TESTING PROGRAM PLAN - VALVES TABLE 2.0 REV 20 (2003)

ASME/ANSI OM-1987 (INCLUDING OMa-1988 ADDENDA) PAGE 44 OF 52 LIQUID RADWASTE SYSTEM P& ID NO. 1020 19 VALVE VALVE P & ID VLV VLV VLV VLV ACT NRM TST TST STR REL PROC NUMBER DESCRIPTION COORD CLS CAT SIZ TYP TYP POS REQ FRQ TIM REQ NO. REMARKS FCV-258 RCIT GAS ANAL ISOL IC 38-B 2 A 1/2 BA A 0 PI 2Y NA V-205 LT J c V-651D EF Q 1Oc V-3S3 FCV-260 N2 TO RCDT ISOL OC 38-C 2 A 3/4 BA A 0 PI 2Y NA V-2J5 LT J c V-652D EF Q 1Oc V-3S3 FCV-500 CONT SUMP DISCH ISOL IC 38-D 2 A 2 BA A 0 PI 2 NA V-205 LT i c V-649 EF Q I oc V-3S3 FCV-501 CONT SUMP DISCH ISOL OC 39-D 2 A 2 BA A 0 PI 2Y NA V-2J5 LT J c V-649 EF Q 1oc V-3S3 FCV-696 RX CAV SUMP SMPL SUP ISO IC 38-B 2 A 3/8 GL S C PI 2Y NA V-682A LT R c V-682A EF CS 1o CS25 V-3r5 FCV-697 RX CAV SUMP SMPL SUP ISO OC 39-B 2 A 3/8 GL S C PI 2Y NA V-682A LT R c V-682A EF CS 100 CS25 V-315 10006620.1ST 40MIS 60

.6 C PACIFIC GAS & ELECTRIC COMPANY DIABLO CANYON POWER PLANT - UNITS I & 2 INSERVICE TESTING PROGRAM PLAN - VALVES TABLE 2.0 REV 20 (2003)

ASME/ANSI OM- 1987 (INCLUDING OMa- 1988 ADDENDA) PAGE 45 OF 52 LIQUID RADWASTE SYSTEM P& ID NO. 1020 19 VALVE VALVE P & ID VLV VLV VLV VLV ACT NRM TST TST STR REL PROC NUMBER DESCRIPTION COORD CLS CAT SIZ TYP TYP POS REQ FRQ TIM REQ NO. REMARKS flveY W"rtln vm DrIIDI i Int 1 tt I. t1ft A A Itl IA *£ I I _ WI A tQms vt 0IIJ K:rUrL wi Irumir IULLUC z A It Ul W M1 LA, LI J c v -oqo r~abivr 8787 REFUEL WTR PURIF ISOL OC 38-D 2 A 4 Di M LC LT J C V-646 PASSIVE 8795 REFUEL WTR PURIF ISOL IC 38-C 2 A 4 DI M LC LT J C V-646 PASSIVE 8796 REFUEL WTR PURIF ISOL IC 38-D 2 A 4 Di M LC LT J c V-646 PASSIVE 10006620.1ST 40MIS 61

r C C PACIFIC GAS & ELECTRIC COMPANY DIABLO CANYON POWER PLANT - UNITS I & 2 INSERVICE TESTING PROGRAM PLAN - VALVES TABLE 2.0 REV 20 (2003)

ASME/ANSI OM-1987 (INCLUDING OMa-1988 ADDENDA) PAGE 46 OF 52 VENTILATION AND AIR CONDITIONING SYSTEM P& ID NO. 1020 23 VALVE VALVE P&ID VLV VLV VLV VLV ACT NRM TST TST STR REL PROC NUMBER DESCRIPTION COORD CLS CAT SIZ TYP TYP POS REQ FRQ TIM REQ NO. REMARKS VAC-I CHIP SUP FAN-I ISOL OC 45-A 2 A 4 GA M LC LT R c V-683 (45A-D)

VAC-2 CHP SUP FAN-2 ISOL OC 34-A 2 A 4 GA M LC LT R C V-683 (45A-E)

VAC-21 CONT AIR SMPL RTN ISOL IC 44-B 2 A,C 2 CK N 0 LT R C V-668

( I I-C) EC R C RR2 V-668 VAC-1 16 CONT AIR SMPL POST LOCA 44-C 2 A,C 3/8 CK N C LT R C V-682B RTN ISOL IC (I I I-D) EC R C RR2 V-682B VAC-200 CHP SUP ISOL IC CK 35-A 2 A,C 4 CK N C LT R C V-683 (48A-D)

VAC-201 CHP SUP ISOL IC CK 35-A 2 A,C 4 CK N C LT R C V-683 (48A-C)

VAC-252 CONT H2 SAMPLE RTN CK IC 44-D 2 AC 3/8 CK N C LT R c V-678 (131-B) EC R 0 RR2, V-678 R18 EP CS 0 CS25 V-3T3 VAC-253 CONT H2 SAMPLE RTN CK IC 44-E 2 A,C 3/8 CK N C LT R c V-678 (131-D) EC R 0 RR2, V-678 R18 EP CS 0 CS25 V-3T3 FCV-235 CONT H2 SAMPLE SUP ISOL IC 44-C 2 A 3/8 GL S LC Pi 2Y NA V-678 (131-A) LT R c V-678 EF CS 10o CS25 V-3T3 10006620.1ST 40MIS 62

C ( C PACIFIC GAS & ELECTRIC COMPANY DIABLO CANYON POWER PLANT - UNITS I & 2 INSERVICE TESTING PROGRAM PLAN - VALVES TABLE 2.0 REV 20 (2003)

ASME/ANSI OM-1987 (INCLUDING OMa-1988 ADDENDA) PAGE 47 OF 52 VENTILATION AND AIR CONDITIONING SYSTEM P& ID NO. 1020 23 VALVE VALVE P & ID VLV VLV VLV VLV ACT NRM TST TST STR REL PROC NUMBER DESCRIPTION COORD CLS CAT SIZ TYP TYP POS REQ FRQ TIM REQ NO. REMARKS FCV-236 CONt H2 SAMPLE SUP ISOL OC 46-C 2 A 3/8 GL S LC Pi 2Y NA V-678 (133-A) LT R c V-678 EF CS 100 CS25 V-3T3 FCV-237 CONT H2 SAMPLE RTN ISOL OC 46-D 2 A 3/8 GL S LC Pi 2Y NA V-678 (133-B) LT R c V-678 EF CS 100 CS25 V-3T3 FCV-238 CONT H2 SAMPLE SUP ISOL IC 46-D 2 A 3/8 GL S LC Pi NA V-678 (131-C) LT R c V-678 EF CS 100 CS25 V-3T3 FCV-239 CONT H2 SAMPLE SUP ISOL OC 46-D 2 A 3/8 GL S LC PI 2Y NA V-678 (133-C) LT R c V-678 EF CS Io CS25 V-3T3 FCV-240 CONT H2 SAMPLE RTN ISOL OC 46-E 2 A 3/8 GL S LC Pi 2Y NA V-678 (30-B) LT R c V-678 EF CS 100 CS25 V-3T3 FCV-654 INCOR CHILL WTR SUP ISOL OC 34-D 2 A 2 BA A C Pi 2Y NA V-2J7 (30-B) LT J c V-682D EF Q 1Oc V-3S4 FCV-655 INCOR CHILL WTR SUP ISOL IC 35-D 2 A 2 BA A C P1 2Y NA V-204 (30-B) LT J c V-682D EF Q 1Oc V-3S4 FCV-656 INCOR CHILL WTR SUP ISOL OC 34-D 2 A 2 BA A C Pi 2Y NA V-2J7 (30-B) LT J c V-682D EF Q 1oc V-3S4 10006620.1St 40MIS 63

(7 ( C PACIFIC GAS & ELECTRIC COMPANY DIABLO CANYON POWER PLANT - UNITS I & 2 INSERVICE TESTING PROGRAM PLAN - VALVES TABLE 2.0 REV 20 (2003)

ASME/ANSI OM-1987 (INCLUDING OMa-1988 ADDENDA) PAGE 48 OF 52 VENTILATION AND AIR CONDITIONING SYSTEM P& ID NO. 1020 23 VALVE VALVE P & ID VLV VLV VLV VLV ACT NRM TST TST STR REL PROC NUMBER DESCRIPTION COORD CLS CAT SIZ TYP TYP POS REQ FRQ TIM REQ NO. REMARKS FCV-657 INCOR CHILL WTR SUP ISOL IC 35-D 2 A 2 BA A C Pi 2Y NA V-204 (30-B) LT J c V-682D EF Q IOc V-3S4 FCV-658 CHP EXH SYS #2 DISCH ISO IC 35-B 2 A 4 GA E LC PI 2Y NA V-2X (I4SA-C) LT J c V-681 EF CS 15o CS25 V-3T3 FCV-659 CHP EXH SYS #I DISCH ISO IC 35-B 2 A 4 GA E LC Pi NA V-2X (34-C) LT J c V-657 EF CS 150 CS25 V-3T3 FCV-660 CONT PURGE SUP ISOL IC 35-C 2 A 48 BV A C PI 2Y NA V-2Q (34-C) LT S c V-661 *Per Tech Spec EF CS 2c CS29 V-3T7 FCV-661 CONT PURGE SUP ISOL OC 34-C 2 A 48 BV A C Pi 2Y NA V-2EI LT S c V-661 Per Tech Spec EF CS 2c CS29 V-3T7 FCV-662 CONT EXCESS PREStVAC RLF 35-C 2 A 12 BV A C Pi 2Y NA V-2Q ISOL IC I(34-C) LT S c V-663 *Per Tech Spec EF Q Sc V-3T6 10006620.1ST 40MIS 64

{ C PACIFIC GAS & ELECTRIC COMPANY DIABLO CANYON POWER PLANT - UNITS I & 2 INSERVICE TESTING PROGRAM PLAN - VALVES TABLE 2.0 REV 20 (2003)

ASME/ANSI OM-1987 (INCLUDING OMa-1988 ADDENDA) PAGE 49 OF 52 VENTILATION AND AIR CONDITIONING SYSTEM P& ID NO. 1020 23 VALVE VALVE P & ID VLV VLV VLV VLV ACT NRM TST TST STR REL PROC NUMBER DESCRIPTION COORD CLS CAT SIZ TYP TYP POS REQ FRQ TIM REQ NO. REMARKS FCV-663 CONT XCESS PRES RLF ISO OC 31-C 2 A 12 BV A C Pi 2Y NA V-2E3 (34-C) LT S c V-663 Per Tech Spec EF Q 5c V-3T6 FCV-664 CONT VAC RLF OC 32-C 2 A 12 BV A C Pi 2Y NA V-2E3 (34-C) LT S c V-663 Per Tech Spec EF Q 5c V-3T6 FCV-668 CHP EXH SYS #2 DISCH ISO OC 34-B 2 A 4 GA E LC Pi 2Y NA V-2X (47A-C) LT J c V-681 EF CS 15o CS25 V-3T3 FCV-669 CHP EXH SYS #I DISCH ISO OC 34-B 2 A 4 GA E LC Pi 2Y NA V-2X (47A-B) LT J c V-657 EF CS 150 CS25 V-3T3 FCV-678 CONT AIR SAMPLE SUP ISOL IC 44-A 2 A I BA A 0 Pi 2Y NA V-203 (III-B) LT J c V-668 EF Q 1Oc V-31 10006620.1ST 40MIS 65

C C PACIFIC GAS & ELECTRIC COMPANY DIABLO CANYON POWER PLANT - UNITS I & 2 INSERVICE TESTING PROGRAM PLAN - VALVES TABLE 2.0 REV 20 (2003)

ASME/ANSI OM-1987 (INCLUDING OMa-1988 ADDENDA) PAGE 50 OF 52 VENTILATION AND AIR CONDITIONING SYSTEM P& ID NO. 1020 23 VALVE VALVE P & ID VLV VLV VLV VLV ACT NRM TST TST STR REL PROC NUMBER DESCRIPTION COORD CLS CAT SIZ TYP TYP POS REQ FRQ TIM REQ NO. REMARKS FCV-679 AIR SAMPLE SUP ISOL OC 46-A 2 A I BA A O PI 2Y NA V-2J1I

( 113-B) LT J c V-668 EF Q l Oc V-3T1 FCV-681 AIR SAMPLE RETURN ISOL OC 46-B 2 A I BA A 0 PI 2Y NA V-2J I

( 113-C) LT J c V-668 EF Q 10c V-3TI FCV-698 AIR SAMPLE POST LOCA SUP 44-B 2 A 3/8 GL S C PI 2Y NA V-682B ISOL OC ( III-C) LT R c V-682B EF Q I Oo/c V-3T4 FCV-699 AIR SAMPLE POST LOCA SUP 46-B 2 A 3/8 GL S C PI 2Y NA V-682B ISOL OC ( 113-C) LT R c V-682B EF Q I Do/c V-3T4 FCV-700 AIR SAMPLE POST LOCA SUP 35-C 2 A 3/8 GL S C PI 2Y NA V-682B ISOL OC ((34-C) LT R c V-682B EF Q I Oo/c V-3T4 RCV-I I PURGE EXHAUST ISOL IC 34-C 2 A 48 BV A C PI 2Y NA V-2Q LT. S c V-662 *Per Tech Spec EF CS 2c CS29 V-3T7 RCV-12 PURGE EXHAUST ISOL OC 34-C 2 A 48 BV A C PI 2Y NA V-2E2 LT S c V-662 Per Tech Spec EF CS 2c CS29 V-3T7 10006620.1ST 40MIS 66

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ASME/ANSI OM-1987 (INCLUDING OMa-1988 ADDENDA) PAGE 51 OF 52 COMPRESSED AIR SYSTEMS P& ID NO. 1020 25 VALVE VALVE P & ID VLV VLV VLV VLV ACT NRM TST TST STR REL PROC NUMBER DESCRIPTION COORD CLS CAT SIZ TYP TYP POS REQ FRQ TIM REQ NO. REMARKS AIR-S-1 14 CONT SERV AIR SUP ISOL IC 41-D 2 A,C 3 CK N C LT J c V-656 (48-D)

AIR-S-200 CONT SERV AIR SUP ISOL OC 42-D 2 A 3 BA M LC LT J c V-656 PASSIVE (47-D)

AIR-1-585 CONT NORM INST AIR SUP 42-C 2 A 1.5 DI M LC LT R C V-654 PASSIVE ISOL BYPASS OC (47-C)

AIR-1-587 CONT NRM INST AIR SUP CK IC 42-D 2 A,C 2 CK N 0 LT C V-654 (47-D) EC R C RR2 V-654 FCV-584 CNT NRM INST AIR SUP ISO OC 42-C 2 A 2 BA A 0 pI 2Y NA V-2J7 (47-C) LT C V-654 EF Q lOc V-3S4 10006620.1ST 40MIS 67

C (7 C

PACIFIC GAS & ELECTRIC COMPANY DIABLO CANYON POWER PLANT - UNITS I & 2 INSERVICE TESTING PROGRAM PLAN - VALVES TABLE 2.0 REV 19(2002)

ASME/ANSI OM-1987 (INCLUDING OMa-1988 ADDENDA) PAGE 52 OF 52 REMARKS

1. 1 The backflow safety function of check valves FW-348, 350, 352, is not tested, instead credit is taken for closing the manual isolation valves, FW121, 159, and 180, pfior to realigning to the raw water storage reservoir per Operating Procedure, OP D-l :V.

1. 2 The AFW pumps' discharge check valves FW-361, 362. and 363, share the safety function of preventing backflow with the second-off checks, FW-369 through 376. Due to the difficulty of testing these valves only the second-off checks will be quarterly tested in the closed direction.

1. 3 The leak tests for valves FW-367, 368, 531, and 532, are not required by Code as these valves do not have a safety related function to prevent back leakage. The leak test and the categorization as "A,C" is based on a corrective action in NCR DCI-91-TN-N002.

1. 4 Deleted.

1. 5 FCV- 11 OA does not have an active safety function. The safety related boration flow path is through 8104 and the redundant flow path is from the RWST.

However, in the Appendix R and Hosgri evaluations credit was taken for this valve to open or fail open so this valve is being administratively included in the ST program as a conservative measure since it may be considered a licensing commitment.

1. 6 Deleted.

1. 7 The open safety function of check valve CVCS-8440 is verified during normal operations.

10006620.1ST 40MIS 68

PACIFIC GAS & ELECTRC COMPANY DIABLO CANYON POWER PLANT - UNITS I & 2 INSERVICE TESTING PROGRAM PLAN - PUMPS AND VALVES TABLE 2.1 ASME/ANSI OM-1987 (INCLUDING OMa-1988 ADDENDA) REV 20 (2003)

COLD SHUTDOWN FREQUENCY JUSTIFICATION PAGE I OF 33 NO. V-CS1 Valves: FW-367 Steam Generator #2 Main Feedwater Check FW-368 Steam Generator #1 Main Feedwater Check FW-531 Steam Generator #3 Main Feedwater Check FW-532 Steam Generator #4 Main Feedwater Check Category: A/C Code Class: 2 Valves: FCV438 Steam Generator #I Feedwater Isolation Valve FCV439 Steam Generator #2 Feedwater Isolation Valve FCV-440 Steam Generator #3 Feedwater Isolation Valve FCV-441 Steam Generator #4 Feedwater Isolation Valve Category: B Code Class: 2 Function:

The check valves have an active function to close to prevent backflow so that AFW pump discharge flow will be directed to the steam generators as required when the AFW system is actuated.

The isolation valves have an active safety function to close to terminate continued feedwater flow to the steam generators or to a faulted feedwater line inside containment as assumed in the plant accident analysis.

Basis:

These Main Feedwater Check Valves and Feedwater Isolation Valves cannot be exercised during power operation because closing these valves would require securing feed flow to a steam generator which would result in a reactor trip. Three loop operation has not been analyzed for at Diablo Canyon Power Plant and is not allowed.

Justification:

Cold shutdown frequency testing is per Part 10, paragraph 4.2.1.2(c) and 4.3.2.2(c).

10006620.1ST 40MIS 69

PACIFIC GAS & ELECTRIC COMPANY DIABLO CANYON POWER PLANT - UNITS 1 & 2 INSERVICE TESTING PROGRAM PLAN - PUMPS AND VALVES TABLE 2.1 ASME/ANSI OM-1987 (INCLUDING OMa-198S ADDENDA) REV 20 (2003)

COLD SHUTDOWN FREQUENCY JUSTIFICATION PAGE 2 OF 33 NO. V-CS2 Valves: FW-348 Aux Feedwater Pump #1 Suction Check Valve from the CST FW-350 Aux Feedwater Pump #2 Suction Check Valve from the CST FW-352 Aux Feedwater Pump #3 Suction Check Valve from the CST Categorv: C Code Class: 3 Function:

These valves have an active safety function in the open direction to permit the flow of water from the CST to the AFW pumps' suction. They also have a safety function to close to maintain AFW pump suction when this suction is aligned to the raw water reservoir.

Basis:

These AFW supply check valves cannot be full stroke exercised during power operation because the only available flow path is into the steam generators which could result in thermal shock to the associated piping and fittings. These valves will be full stroked open during a shutdown to, or a startup from, a cold shutdown condition.

The backflow safety function of these check valves is not tested, instead credit is taken for closing the manual isolation valves, FW- 121, 159, and 180, when realigning to the raw water storage reservoir per Operating Procedure, OP D- I:V.

Justification:

Cold shutdown frequency testing is per Part 10, paragraph 4.3.2.2(c).

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PACIFIC GAS & ELECTRC COMPANY DIABLO CANYON POWER PLANT - UNITS I & 2 INSERVICE TESTING PROGRAM PLAN - PUMPS AND VALVES TABLE 2.1 ASME/ANSI OM-1987 (INCLUDING OMa-1988 ADDENDA) REV 20 (2003)

COLD SHUTDOWN FREQUENCY JUSTIFICATION PAGE 3 OF 33 NO. V-CS3 Valves: FW-361 Aux Feedwater Pump #I Discharge Check Valve FW-362 Aux Feedwater Pump #2 Discharge Check Valve FW-363 Aux Feedwater Pump #3 Discharge Check Valve Category: C Code Class: 3 Valves: FW-369 Aux Feedwater Pump #1 to Steam Generator #I Check Valve FW-370 Aux Feedwater Pump #2 to Steam Generator #I Check Valve FW-371 Aux Feedwater Pump #1 to Steam Generator #2 Check Valve FW-372 Aux Feedwater Pump #2 to Steam Generator #2 Check Valve FW-373 Aux Feedwater Pump #1 to Steam Generator #3 Check Valve FW-374 Aux Feedwater Pump #3 to Steam Generator #3 Check Valve FW-375 Aux Feedwater Pump #1 to Steam Generator #4 Check Valve FW-376 Aux Feedwater Pump #3 to Steam Generator #4 Check Valve FW-377 Steam Generator #I Aux Feedwater 1st off Check Valve FW-378 Steam Generator #2 Aux Feedwater 1st off Check Valve FW-379 Steam Generator #3 Aux Feedwater 1st off Check Valve FW-380 Steam Generator #4 Aux Feedwater 1st off Check Valve Category: C Code Class: 2 Function:

These valves have an active safety function in the open direction to permit the flow of water from the AFW pump discharge lines to the steam generators. Second off check valves FW-369, FW-370, FW-371, FW-372, FW-373, FW-374, FW-375, and FW-376 also have a safety function to close to prevent the backflow of feedwater through an idle AFW pump.

Basis:

These Auxiliary Feedwater Supply Check Valves cannot be full stroke exercised during power operation because the only available flow path is into the steam generators which could result in thermal shock to the associated piping and fittings. These valves will be full stroke exercised during a shutdown to, or a startup from, a cold shutdown condition.

Justification:

Cold shutdown frequency testing is per Part 10, paragraph 4.3.2.2(c).

10006620.1ST 40MIS 71

PACIFIC GAS & ELECTRIC COMPANY DIABLO CANYON POWER PLANT - UNITS I & 2 INSERVICE TESTING PROGRAM PLAN - PUMPS AND VALVES TABLE 2.1 ASME/ANSI OM-1987 (INCLUDING OMa-1988 ADDENDA) REV 20 (2003)

COLD SHUTDOWN FREQUENCY JUSTIFICATION PAGE 4 OF 33 NO. V-CS4 Valves: MS-5 166 Steam Generator #2 to Aux Feedwater Pump #I Check Valve MS-5167 Steam Generator #3 to Aux Feedwater Pump #1 Check Valve Category: C Code Class: 2 Function:

These valves have an active safety function to-apen to allow steam flow to the AFW pump turbine. They also have a safety function to prevent the backflow of steam from an unfaulted steam generator escaping out of the break in a faulted steam generator.

Basis:

These check valves cannot be full stroke exercised during power operation because this would require operating the turbine-driven AFW pump at rated speed and the only available flow path for AFW is into the steam generators which could result in thermal shock to the associated piping and fittings. These valves will be part stroked on a quarterly frequency with the pump operating on its recirculation flow path. Full stroke exercising will be performed during a shutdown to. or a startup from, a cold shutdown condition.

Closure testing is covered in Valve Relief Request #11.

Justification:

Cold shutdown frequency testing is per Part 10, paragraph 4.3.2.2(b).

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PACIFIC GAS & ELECTRIC COMPANY DIABLO CANYON POWER PLANT - UNITS & 2 INSERVICE TESTING PROGRAM PLAN - PUMPS AND VALVES TABLE 2.1 ASME/ANSI OM-1987 (INCLUDING OMa-1988 ADDENDA) REV 20 (2003)

COLD SHUTDOWN FREQUENCY JUSTIFICATION PAGE 5 OF 33 NO. V-CS5 Valves: FCV-4 1 Steam Generator #I Main Steam Isolation Valve FCV-42 Steam Generator #2 Main Steam Isolation Valve FCV-43 Steam Generator #3 Main Steam Isolation Valve FCV44 Steam Generator #4 Main Steam Isolation Valve Categorv: B Code Class: 2 Function:

These valves have an active safety function to automatically close on high steam flow, coincident with either low-low T(avg) or low steam pressure, or on a high-high containment pressure signal.

Basis:

These valves cannot be full stroke exercised during power operation because this would require securing steam from a steam generator which would result in a reactor trip, and most likely a safety injection. Also, three loop operation has not been analyzed for Diablo Canyon Power Plant and is not allowed.

Part stroke testing capability does exist for these valves but is not considered practical, since extremely limited (60 max., 2° nominal) valve motion is allowed due to the valve design which only provides verification that the valve is not frozen in the open position. Additionally, as a result of the valve design, performing partial stroke testing exposes the plant to an inadvertent Reactor Trip and/or Safety Injection should the valve stroke more than 6° (resulting in a flow assisted closure of the valve).

These valves will be full stroke exercised on a cold shutdown frequency.

Justification:

Cold shutdown frequency testing is per Part 10, paragraph 4.2.1.2(c).

10006620.1ST 40MIS 73

PACIFIC GAS & ELECTRIC COMPANY DIABLO CANYON POWER PLANT - UNITS I & 2 INSERVICE TESTING PROGRAM PLAN - PUMPS AND VALVES TABLE b.l ASME/ANSI OM-1987 (INCLUDING OMa-1988 ADDENDA) REV 20 (2003)

COLD SHUTDOWN FREQUENCY JUSTIFICATION PAGE 6 OF 33 NO. V-CS6 Valves: PCV455C Pressurizer Power Operated Relief Valve PCV456 Pressurizer Power Operated Relief Valve PCV-474 Pressurizer Power Operated Relief Valve Categorv: B Code Class: I Function:

The PORVs have an active safety function to open for steam generator tube rupture accident mitigation and also for RCS low temperature overpressure protection.

Basis:

The PORVs should not be exercised during power operation by NRC direction. The NRC's current position is that these valves will be full stroke exercised during the approach to cold shutdown.

Justification:

Cold shutdown frequency testing is per Part 10, paragraph 4.2.1 *2(c).

10006620.1ST 40MIS 74

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INSERVICE TESTING PROGRAM PLAN - PUMPS AND VALVES TABLE 2.1 ASME/ANSI OM-1987 (INCLUDING OMa-1988 ADDENDA) REV 20 (2003)

COLD SHUTDOWN FREQUENCY JUSTIFICATION PAGE 7 OF 33 NO. V-CS8 Valves: LCV-I 12B Volume Control Tank Outlet Isolation Valve LCV-I 12C Volume Control Tank Outlet Isolation Valve Categor: B Code Class: N/A Function:

These valves have an active safety function to Lose to isolate the volume control tank from the suction of the charging pumps upon the receipt of a safety injection signal.

Basis:

These isolation valves should not be exercised during power operation because failure of either valve in the closed position would result in a loss of reactor system level control or injecting 2000 ppm boric acid solution from the RWST into the reactor coolant system, resulting in a possible plant shutdown. See also NRC SER dated 1/31/94 addressing LA 86 and 87.

Justification:

Cold shutdown frequency testing is per Part 10, paragraph 4.2.1.2(c).

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PACIFIC GAS & ELECTRIC COMPANY DIABLO CANYON POWER PLANT - UNITS I & 2 INSERVICE TESTING PROGRAM PLAN - PUMPS AND VALVES TABLE 2.1 ASME/ANSI OM-1987 (INCLUDING OMa-1988 ADDENDA) REV 20 (2003)

COLD SHUTDOWN FREQUENCY JUSTIFICATION PAGE 8 OF 33 NO. V-CS9 Valves: 8100 Reactor Coolant Pump Seal Water Return Isolation Valve, Outside Containment 8112 Reactor Coolant Pump Seal Water Return Isolation Valve. Inside Containment Category: A Code Class: 2 Function:

These valves have an active safety function to close to isolate the seal water return line containment penetration upon receipt of a Phase A containment isolation signal.

Basis:

These isolation valves cannot be exercised during power operation because this would challenge the relief valve in the RCP seal water return line. If this relief valve failed in the open position, this would result in unnecessary reactor coolant system leakage. These valves need not be exercised in MODE 5 if the Reactor Coolant Pumps are operating and would need to be stopped and restarted solely to test cold shutdown frequency tested valves. Deferral of testing these valves is allowed per NUREG-1482 paragraph 3.1.1.4.

Justification:

Cold shutdown frequency testing is per Part 10, paragraph 4.2.1.2(c).

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PACIFIC GAS & ELECTRIC COMPANY DIABLO CANYON POWER PLANT - UNITS I & 2 INSERVICE TESTING PROGRAM PLAN - PUMPS AND VALVES TABLE 2.1 i,~ ASME/ANSI OM-1987 (INCLUDING OMa-1988 ADDENDA) REV 20 (2003)

COLD SHUTDOWN FREQUENCY JUSTIFICATION PAGE 9 OF 3 NO. V-CSIO Valves: 8105 Centrifugal Charging Pumps' Recirculation Isolation Valve 8106 Centrifugal Charging Pumps' Recirculation Isolation Valve Categon: B Code Class: 2 (8106), N/A (8105)

Function:

These valves have an active safety function to -,loseto isolate the high pressure safety injection flow path from the CVCS during safety injection system operation following a LOCA.

Basis:

These valves should not be exercised during power operation because failure of either valve in the closed position could result in pump damage if a secondary system accident occurred.

Justification:

Cold shutdown frequency testing is per Part 10, paragraph 4.2.1.2(c).

10006620.1ST 40MIS 77

PACIFIC GAS & ELECTRIC COMPANY DIABLO CANYON POWER PLANT - UNITS I & 2 INSERVICE TESTING PROGRAM PLAN - PUMPS AND VALVES TABLE 2.1 ASME/ANSI OM-1987 (INCLUDING OMa-1988 ADDENDA) REV 20 (2003)

COLD SHUTDOWN FREQUENCY JUSTIFICATION PAGE 10 OF33 NO. V-CSI1 Valves: 8107 Charging Line Isolation Valve 8108 Charging Line Isolation Valve Category: B Code Class: 2 Function:

These redundant, motor-operated gate valves hive an active safety function to close to isolate the normal charging flow path from the high pressure safety injection flow path upon receipt of a safety injection signal.

Basis:

These valves should not be exercised during power operation because failure of either valve in the closed position could result in loss of reactor coolant system level control, which could result in a plant shutdown.

Also, failure of either of these valves in a closed position would place the plant in an LCO action statement due to a loss of the boration flow path from the boric acid tanks. See also NRC SER dated 1/31/94 addressing LA 86 and 87.

Justification:

Cold shutdown frequency testing is per Part I0, paragraph 4.2.1.2(c).

10006620.1ST 40MIS 78

PACIFIC GAS & ELECTRIC COMPANY DIABLO CANYON POWER PLANT - UNITS & 2 INSERVICE TESTING PROGRAM PLAN - PUMPS AND VALVES TABLE 2.1 ASME/ANSI OM-1987 (INCLUDING OMa-1988 ADDENDA) REV 20 (2003)

COLD SHUTDOWN FREQUENCY JUSTIFICATION PAGE 11 OF 33 NO. V-CS12 Valves: 8145 Pressurizer Auxiliary Spray Valve 8148 Pressurizer Auxiliary Spray Bypass Valve Category: B Code Class: I Valves: 8377 Pressurizer Auxiliary Spray Check Valve Category: C Code Class: I Function:

Air operated globe valves 8145 and 8148, along with check valve 8377, have an active safety function to open during plant cooldown to cooldown the pressurizer when normal pressurizer spray is inoperable. This is not an accident mitigation function but a safe shutdown function following a Hosgri earthquake.

Basis:

These valves should not be exercised during power operation because failure of either valve in the open position could result in a loss of reactor coolant system pressure control which could result in a plant shutdown.

Justification:

Cold shutdown frequency testing is per Part 10, paragraph 4.2.1.2(c) and 4.3.2.2(c).

10006620.1ST 40MIS 79

PACIFIC GAS & ELECTRIC COMPANY DIABLO CANYON POWER PLANT - UNITS I & 2 INSERVICE TESTING PROGRAM PLAN - PUMPS AND VALVES TABLE 2.1 ASMEIANSI OM-1987 (INCLUDING OMa-1988 ADDENDA) REV 20 (2003)

COLD SHUTDOWN FREQUENCY JUSTIFICATION PAGE 12 OF 33 NO. V-CS13 Valves: 8152 Letdown Line Isolation Valve, Outside Containment Category: A Code Class: 2 Function:

This air operated globe valve has an active safety function to close to isolate letdown on a high room temperature in the letdown heat exchanger rocn. This valve also has the safety function of providing containment isolation.

Basis:

This valve should not be.exercised during power operation because failure of the valve in the closed position could result in a loss of reactor coolant system level control which could result in a plant shutdown. See also NRC SER dated 1/31/94 addressing LA 86 and 87.

Justification:

Cold shutdown frequency testing is per Part 10, paragraph 4.2.1.2(c).

10006620.1ST 40MIS 80

PACIFIC GAS & ELECTRIC COMPANY DIABLO CANYON POWER PLANT - UNITS I & 2 INSERVICE TESTING PROGRAM PLAN - PUMPS AND VALVES TABLE 2.1 ASME/ANSI OM-1987 (INCLUDING OMa-1988 ADDENDA) REV 20 (2003)

COLD SHUTDOWN FREQUENCY JUSTIFICATION PAGE 13 OF 33 NO. V-CS14 Valves: 8802A Safety Injection Pump #1 Discharge Isolation Valve, Outside Containment 8802B Safety Injection Pump #2 Discharge Isolation Valve, Outside Containment Cateeory: A Code Class: 2 Function:

These motor operated gate valves have an acti .iesafety function to open to provide a flow path for the safety injection pumps in the Hot Leg recirculation mode.

Basis:

These valves cannot be exercised during power operation because they are required to be closed with power to the valve operators removed by Technical Specification SR 3.5.2.1. If these valves were opened during power operation and an accident were to occur, safety injection flow would go to the hot legs instead of the cold legs. The safety analysis has analyzed for flow going to the cold legs and not the hot legs.

Justification:

Cold shutdown frequency testing is per Part 10, paragraph 4.2.1.2(c).,

10006620.1ST 40MIS 81

PACIFIC GAS & ELECTRIC COMPANY DIABLO CANYON POWER PLANT - UNITS I & 2 INSERVICE TESTING PROGRAM PLAN - PUMPS AND VALVES TABLE 2.1 ASME/ANSI OM-1987 (INCLUDING OMa-1988 ADDENDA) REV 20 (2003)

COLD SHUTDOWN FREQUENCY JUSTIFICATION PAGE 14 OF 33 NO. V-CS15 Valves: 8809A RHR to Cold Legs 1&2 Isolation Valve 8809B RHR to Cold Legs 3&4 Isolation Valve Categorv: B Code Class: 2 Function:

These motor operated gate valves have an active safety function to close during hot leg recirculation. These valves are exempt from type C leak testing per Appendix J, section III.C.3. They also have a passive safety function to remain open to provide a flow path from the RHR system to the SIS/RCS cold leg injection lines.

These valves are normally open with the power to the actuators removed during power operations.

Basis:

These valves cannot be exercised during power operation because they are required to be open with power to the valve operators removed by Technical Specification SR 3.5.2.1.

Justification:

Cold shutdown frequency testing is per Part 10, paragraph 4.2.1.2(c).

10006620.1ST 40MIS 82

PACIFIC GAS & ELECTRIC COMPANY DIABLO CANYON POWER PLANT - UNITS I & 2 INSERVICE TESTING PROGRAM PLAN - PUMPS AND VALVES TABLE 2.1 A_, ASME/ANSI OM-1987 (INCLUDING OMa-1988 ADDENDA) REV 20 (2003)

COLD SHUTDOWN FREQUENCY JUSTIFICATION PAGE 15 OF 33 NO. V-CS16 Valves: 8835 Safety Injection to Cold Legs Isolation Valve Category: B Code Class: 2 Function:

This motor operated gate valve has an active safety function to close when placing the ECCS in the hot leg recirculation mode of safety injection. This va.ve is exempt from type C leak testing per Appendix J, section II.C.3.

Basis:

This valve cannot be exercised during power operation because it is required to be open with power to the valve operator removed by Technical Specification SR 3.5.2.1. Also, failure of this valve in the closed position would result in the safety injection system being not OPERABLE.

Justification:

Cold shutdown frequency testing is per Part 10, paragraph 4.2.1.2(c).

10006620.1ST 40MIS 83

PACIFIC GAS & ELECTRIC COMPANY DIABLO CANYON POWER PLANT - UNITS I & 2 INSERVICE TESTING PROGRAM PLAN - PUMPS AND VALVES TABLE 2.1 ASME/ANSI OM-1987 (INCLUDING OMa-1988 ADDENDA) REV 20 (2003)

COLD SHUTDOWN FREQUENCY JUSTIFICATION PAGE 16 OF 33 NO. V-CS17 Valves: 8974A Safety Injection Pumps Recirculation to the Refueling Water Storage Tank Isolation Valve 8974B Safety Injection Pumps Recirculation to the Refueling Water Storage Tank Isolation Valve Cateronr: B Code Class: 2 (8974B), N/A (8974A)

Function:

These motor operated globe valves have an active safety function-to close via an interlock prior to either 8804A or 8804B opening.

Basis:

These valves cannot be exercised during power operation because they are required to be open with power to the valve operators removed by Technical Specification SR 3.5.2.1. Also, the failure of one of these valves in the closed position could result in damage to the safety injection pumps, if an SI signal were to start the pumps during this condition or test, thereby rendering the safety injection system not OPERABLE.

Justification:

Cold shutdown frequency testing is per Part 10, paragraph 4.2.1.2(c).

10006620.1ST 40MIS 84

PACIFIC GAS & ELECTRIC COMPANY DIABLO CANYON POWER PLANT - UNITS I & 2 INSERVICE TESTING PROGRAM PLAN - PUMPS AND VALVES TABLE 2.1 ASMEtANSI OM-1987 (INCLUDING OMa-1988 ADDENDA) REV 20 (2003)

COLD SHUTDOWN FREQUENCY JUSTIFICATION PAGE 17 OF 33 NO. V-CS18 Valves: 8976 RWST to Safety Injection Pumps Suction Isolation Valve Category: B Code Class: 2 Function:

This motor operated gate valve has an active safety function to close to prevent backflow to the refueling water storage tank during the post-LOCA recirculation mode of safety injection.

Basis:

This valve cannot be exercised during power operation because it is required to be open with power to the valve operator removed by Technical Specification SR 3.5.2.1. Also, failure of this valve in the closed position would result in the entire safety injection system being not OPERABLE.

Justification:

Cold shutdown frequency testing is per Part 10, paragraph 4.2.1.2(c).

10006620.1ST 40MIS 85

PACIFIC GAS & ELECTRC COMPANY DIABLO CANYON POWER PLANT - UNITS I & 2 INSERVICE TESTING PROGRAM PLAN - PUMPS AND VALVES TABLE 2.1 ASME/ANSI OM-1987 (INCLUDING OMa-1988 ADDENDA) REV 20 (2003)

COLD SHUTDOWN FREQUENCY JUSTIFICATION PAGE 18 OF 33 NO. V-CS19 Valves: 8980 RWST to RHR Pumps Suction Isolation Valve Category: B Code Class: 2 Function:

This motor operated gate valve has an active safety function to close to prevent backflow into the refueling water storage tank if the downstream check va.ve leaks.

Basis:

This valve cannot be exercised during power operation because it is required to be open with power to the valve operator removed by Technical Specification SR 3.5.2.1. Also, failure of this valve in the closed position would result in the RHR portion of the safety injection system being not OPERABLE.

Justification:

Cold shutdown frequency testing is per Part 10, paragraph 4.2.1.2(c).

10006620.1ST 40MIS 86

PACIFIC GAS & ELECTRIC COMPANY DIABLO CANYON POWER PLANT - UNITS I & 2 INSERVICE TESTING PROGRAM PLAN - PUMPS AND VALVES TABLE 2.1 ASME/ANSI OM-1987 (INCLUDING OMa-1988 ADDENDA) REV 20 (2003)

COLD SHUTDOWN FREQUENCY JUSTIFICATION PAGE 19 OF 33 NO. V-CS20 Valves: 8703 RHR to Hot Legs Isolation Valve Categorv: A Code Class: 2 Function:

This motor operated gate valve has an active safety function to open to provide a flow path for hot leg recirculation after a postulated accident. This %alveis an RCS high pressure to low pressure interface boundary and is therefore leak rate tested every refueling outage per Tech Spec SR 3A.14. 1.

Basis:

This valve cannot be exercised during power operation because it is required to be closed with power to the valve operator removed by Technical Specification SR 3.5.2.1. Also, failure of this valve in the open position would result in diversion of flow from the analyzed flow paths.

Justification:

Cold shutdown frequency testing is per Part. 10, paragraph 4.2.1.2(c).

10006620.1ST 40MIS 87

PACIFIC GAS & ELECITIC COMPANY DIABLO CANYON POWER PLANT - UNITS &

PACIFIC GAS & ELECTRIC COMPANY DIABLO CANYON POWER PLANT UNITS I & 2 -

INSERVICE TESTING PROGRAM PLAN - PUMPS AND VALVES TABLE 2.1 ii ASME/ANSI OM-1987 (INCLUDING OMa-1988 ADDENDA) REV 20 (2003)

COLD SHUTDOWN FREQUENCY JUSTIFICATION PAGE 20 OF 33 NO. V-CS21 Valves: 8730A RHR Pump #1 Discharge Check Valve 8730B RHR Pump #2 Discharge Check Valve Categorv: C Code Class: 2 Function:

These check valves have an active safety function to open to allow flow from the discharge of the RHR pumps.

Basis:

These valves cannot be full stroke exercised during power operation because the RHR pumps do not develop sufficient head to overcome reactor coolant system pressure. They will be part stroked quarterly and full stroked on a cold shutdown frequency.

Justification:

Cold shutdown frequency testing is per Part 10, paragraph 4.3.2.2(b).

10006620.1ST 40MIS 8

PACIFIC GAS & ELECTRIC COMPANY DIABLO CANYON POWER PLANT - UNITS I & 2 INSERVICE TESTING PROGRAM PLAN - PUMPS AND VALVES TABLE 2.1 ASME/ANSI OM-1987 (INCLUDING OMa-1988 ADDENDA) REV 20 (2003)

COLD SHUTDOWN FREQUENCY JUSTIFICATION PAGE 21 OF 33 NO. V-CS22 Valves: 8994A NaOH to Containment Spray Eductor Isolation Valve 8994B NaOH to Containment Spray Eductor Isolation Valve Catezor : B Code Class: 2 Function:

These motor operated gate valves have an acti- e safety function to open to provide a flow path during the ECCS injection phase of containment spray and then during the ECCS recirculation phase up until the time that the RWST low-low level is reached.

Basis:

These valves cannot be exercised during power operation because they could introduce NaOH into the RWST and subsequently into the reactor coolant system causing Na24 activation problems and possible chemical damage to components in the reactor coolant system. To prevent getting NaOH into the RWST, valve 8992 would have to be closed and the line flushed, which would result in the entire Spray Additive System being not OPERABLE.

Justification:

Cold shutdown frequency testing is per Part 10, paragraph 4.2.1.2(c).

10006620.1ST 40MIS 89

PACIFIC GAS & ELECTRIC COMPANY DIABLO CANYON POWER PLANT - UNITS I & 2 INSERVICE TESTING PROGRAM PLAN - PUMPS AND VALVES TABLE 2.1 ASMEIANSI OM-1987 (INCLUDING OMa-1988 ADDENDA) REV 20 (2003)

COLD SHUTDOWN FREQUENCY JUSTIFICATION PAGE 22 OF 33 NO. V-CS23 Valves: 8998A Spray Additive Tank Outlet Check Valve 8998B Spray Additive Tank Outlet Check Valve Categon: A,C Code Class: 2 Function:

These check valves have an active safety function to open to allow the passage of sodium hydroxide solution for eduction into the containment spray flow. They also have a safety function to prevent back leakage. and thereby prevent diluting the educted NaOH solution, in the event.that one of the containment spray pumps fails.

Basis:

These valves cannot be exercised during power operation because the system alignment for testing these check valves would result in the entire Spray Additive System being not OPERABLE.

Justification:

Cold shutdown frequency testing is per Part 10, paragraph 4.2.1.2(c) and 4.3.2.2(c).

10006620.1ST 40MIS 90

PACIFIC GAS & ELECTRC COMPANY DIABLO CANYON POWER PLANT - UNITS I & 2 INSERVICE TESTING PROGRAM PLAN - PUMPS AND VALVES TABLE 2.1 ASMEJANSI OM-1987 (INCLUDING OMa-1988 ADDENDA) REV 20 (2003)

COLD SHUTDOWN FREQUENCY JUSTIFICATION PAGE 23 OF 33 NO. V-CS24 Valves: FCV-355 Component Cooling Water Header C Isolation Valve Category: B Code Class: 3 Valves: FCV-356 CCW to RCP and Reactor Vessel Support Isolation Valve FCV-357 RCP Thermal Barrier CCW Return Isolation Valve FCV-363 RCP Cooler CCW Return Isolation Valve FCV-749 RCP Cooler CCW Return Isolation Valve FCV-750 RCP Thermal Barrier CCW Return Isolation Valve Categowy: A Code Class: 2 Function:

FCV-355 has an active safety function to close to isolate the non-vital CCW header C after an accident to assure adequate flow to the two vital CCW loops.

FCV-356, 357, 363, 749, and 750 each have an active safety function to close to provide containment isolation.

Basis:

These valves cannot be exercised during power operation because this could result in damage to the reactor coolant pumps and a possible plant trip. These valves need not be exercised in MODE 5 if the Reactor Coolant Pumps are operating and would need to be stopped and restarted solely to test cold shutdown frequency tested valves. Deferral of testing these valves is allowed per NUREG-1482 paragraph 3.1.1.4.

Justification:

Cold shutdown frequency testing is per Part 10, paragraph 4.2.1.2(c).

10006620.1ST 40MIS 91

PACIFIC GAS & ELECTRIC COMPANY DIABLO CANYON POWER PLANT - UNITS &

INSERVICE TESTING PROGRAM PLAN - PUMPS AND VALVES TABLE 2.1 ASME/ANSI OM-1987 (INCLUDING OMa-1988 ADDENDA) REV 20 (2003)

COLD SHUTDOWN FREQUENCY JUSTIFICATION PAGE 24 OF 33 NO. V-CS25 Valves: FCV-235 Containment H2 Sample Supply Isolation Valve FCV-236 Containment H2 Sample Supply Isolation Valve FCV-237 Containment H2 Sample Return Isolation Valve FCV-238 Containment H2 Sample Supply Isolation Valve FCV-239 Containment H2 Sample Supply Isolation Valve FCV-240 Containment H2 Sample Supply Isolation Valve FCV-658 Containment H2 Purge Exhaust System #2 Suction Iso Valve FCV-659 Containment H2 Purge Exhaust System #I Suction so Valve FCV-668 Containment H2 Purge Exhaust System #2 Suction Iso Valve FCV-669 Containment H2 Purge Exhaust System #I Suction Iso Valve FCV-696 Reactor Cavity Sump Sample Supply Isolation Valve FCV-697 Reactor Cavity Sump Sample Supply Isolation Valve Category: A Code Class: 2 VAC-252 Containment H2 Sample Return Check Valve VAC-253 Containment H2 Sample Return Check Valve Categorv: A,C Code Class: 2 Function:

These valves have a passive safety function to remain closed to provide containment isolation.

Basis:

These Containment Sample Isolation Valves cannot be exercised during power operation because Technical Specification SR 3.6.3.3 and SR 3.6.3.4 requires these valves to be closed when containment integrity is required, except under strict administrative control. These valves do not receive a containment isolation signal.

VAC-252 and VAC-253 cannot be full stroke exercised during COLD SHUTDOWN because there is not a calibrated flow indicator installed in the Containment Hydrogen Monitoring System. These valves will be part stroke exercised during COLD SHUTDOWNS and full stroked exercised during REFUELING Outages.

Justification:

Cold shutdown frequency testing is per Part 10, paragraph 4.2.1.2(c), 4.3.2.2(c) and 4.3.22(d).

10006620.1ST 40MIS 92

PACIFIC GAS & ELECTRIC COMPANY DIABLO CANYON POWER PLANT - UNITS &2 INSERVICE TESTING PROGRAM PLAN - PUMPS AND VALVES TABLE 2.1 ASME/ANSI OM-1987 (INCLUDING OMa-1988 ADDENDA) REV 20 (2003)

COLD SHUTDOWN FREQUENCY JUSTIFICATION PAGE 25 OF 33 NO. V-CS26 Valves: 8805A Charging Pump Suction Valve 8805B Charging Pump Suction Valve Categorv: B Code Class: 2 Function:

These motor operated gate valves have an active safety function to open to provide a flow path from the refueling water storage tank to the suction of the charging pumps.

Basis:

These valves should not be exercised at power because opening these valves injects highly oxygerated, 2000 ppm borated water from the RWST into the reactor coolant system. Injecting this water results in a negative reactivity addition to the reactor coolant system which could shut the plant down. See also NRC SER dated 1/31/94 addressing LA 86 and 87.

Justification:

Cold shutdown frequency testing is per Part 10, paragraph 4.2.1.2(c).

10006620.1ST 40MIS 93

PACIFIC GAS & ELECTRIC COMPANY DIABLO CANYON POWER PLANT - UNITS I & 2 INSERVICE TESTING PROGRAM PLAN - PUMPS AND VALVES TABLE 2.1 ASME/ANSI OM-1987 (INCLUDING OMa-1988 ADDENDA) REV 20 (2003)

COLD SHUTDOWN FREQUENCY JUSTIFICATION PAGE 26 OF 33 NO. V-CS27 Valves: 8716A RHR Train Crosstie Valves 8716B RHR Train Crosstie Valves Cate o r: B Code Class: 2 Function:

These motor operated gate valves have an acti%e safety function to close to go to the cold leg mode of post-LOCA safety injection. They also have an active safety function to reopen to go to the hot leg mode of post-LOCA safety injection (no stroke time requirement). These valves are exempt from type C leak testing per Appendix J, section III.C.3.

Basis:

These valves cannot be exercised during power operation because failure of the valve in the closed position would result in a loss of RHR injection flow to two of the four RCS loops from a single RHR pump.

Justification:

Cold shutdown frequency testing is per Part 10, paragraph 4.2.1.2(c).

10006620.1ST 40MIS 94

PACIFIC GAS & ELECTRIC COMPANY DIABLO CANYON POWER PLANT - UNITS I & 2 INSERVICE TESTING PROGRAM PLAN - PUMPS AND VALVES TABLE 2.1 ASME/ANSI OM-1987 (INCLUDING OMa-1988 ADDENDA) REV 20 (2003)

COLD SHUTDOWN FREQUENCY JUSTIFICATION PAGE 27 OF 33 NO. V-CS28 Valves: 8742A RHR Heat Exchanger #I Discharge Check Valves 8742B RHR Heat Exchanger #2 Discharge Check Valves Categorv: C Code Class: 2 Function:

These check valves have an active safety funct.on to open to pass RHR flow from the RHR heat exchanger to the RCS. They also have a safety function to close (back flow) to prevent pump to pump interaction.

Basis:

These valves cannot be exercised during power operation because the RHR pumps do not develop sufficient head to overcome reactor coolant system pressure. These valves will be tested for backflow quarterly and for opening on a cold shutdown frequency.

Justification:

Cold shutdown frequency testing is per Part 10, paragraph 4.3.2.2(c).

10006620.1ST 40MIS 95

PACIFIC GAS & ELECTRIC COMPANY DIABLO CANYON POWER PLANT - UNITS I & 2 INSERVICE TESTING PROGRAM PLAN - PUMPS AND VALVES TABLE 2.1 ASME/ANSI OM-1987 (INCLUDING OMa-1988 ADDENDA) REV 20 (2003)

COLD SHUTDOWN FREQUENCY JUSTIFICATION PAGE 28 OF 33 NO. V-CS29 Valves: FCV-660 Containment Purge Supply-isolation Valve (IC)

FCV-661 Containment Purge Supply Isolation Valve (OC)

RCV-I I Containment Purge Exhaust Isolation Valve (IC)

RCV-12 Containment Purge Exhaust Isolation Valve (OC)

Categom: A CodeClass: 2 Function:

These valves have an active safety function to provide containment isolation.

Basis:

These valves are required to be leakrate tested every time they are exercised per Technical Specification (Tech Spec) SR 3.6.3.7. These valves are administratively maintained in their isolation (closed) position during power operations. This ensures they will perform their required safety function and eliminates concerns regarding failure of a post-exercising leak test.

These valves will be full stroke exercised on a cold shutdown frequency.

Justification:

Cold shutdown frequency testing is per Part 10, paragraph 4.2.1.2(c).

10006620.1ST 40MIS 96

PACIFIC GAS & ELECTRIC COMPANY DIABLO CANYON POWER PLANT - UNITS I & 2 INSERVICE TESTING PROGRAM PLAN - PUMPS AND VALVES TABLE 2.1 ASME/ANSI OM-1987 (INCLUDING OMa-1988 ADDENDA) REV 20 (2003)

COLD SHUTDOWN FREQUENCY JUSTIFICATION PAGE 29 OF 33 NO. V-CS30 Valves: 8149A Letdown Orifice Control/Isolation Valve 8149B Letdown Orifice Control/Isolation Valve 8149C Letdown Orifice Control/Isolation Valve Categorv: A Code Class: 2 Function:

These air operated globe valves have an active safety function to close to provide containment isolation and to isolate a high energy letdown line break outside containment upstream of the letdown heat exchanger.

Basis:

These valves will not be exercised during power operation due to the following causes: thermal transients on the regenerative letdown heat exchanger; hydraulic transients on the letdown line; pressure control transients resulting in the lifting of relief valve RV-8117; and charging nozzle temperature transients when charging is isolated during letdown testing. Reference NRC SER dated 1/31/94 addressing LA 86 and 87.

Justification:

Cold shutdown frequency testing is per Part 10, paragraph 4.2.1.2(c).

10006620.1ST 40MIS 97

PACIFIC GAS & ELECTRIC COMPANY DIABLO CANYON POWER PLANT - UNITS I & 2 INSERVICE TESTING PROGRAM PLAN - PUMPS AND VALVES TABLE 2.1 ASME/ANSI OM-1987 (INCLUDING OMa-1988 ADDENDA) REV 20 (2003)

COLD SHUTDOWN FREQUENCY JUSTIFICATION PAGE 30 OF 33 NO. V-CS31 Valves: 8701 RCS Loop 4 to RHR Isolation Valve 8702 RCS Loop 4 to RHR Isolation Valve Category: A Code Class: I Function:

The motor operated double disc gate valves isclate the low pressure Residual Heat Removal System from the High Pressure Reactor Coolant System.

Basis:

These Reactor Coolant System to RHR System Isolation Valves cannot be exercised during power operation because they are required to be closed with power to the valve operators removed by Technical Specification SR 3.5.2.1. Also, failure of this valve to the open position would result in diversion of flow from the analyzed flow paths.

Justification:

Cold shutdown frequency testing is per Part 10, paragraph 4.2.1.2(c).

10006620.1ST 40MIS 98

PACIFIC GAS & ELECTRIC COMPANY DIABLO CANYON POWER PLANT - UNITS I & 2 INSERVICE TESTING PROGRAM PLAN - PUMPS AND VALVES TABLE 2.1

ASME/ANSI OM-1987 (INCLUDING OMa-1988 ADDENDA) REV 20 (2003)

COLD SHUTDOWN FREQUENCY JUSTIFICATION PAGE 31 OF 33 NO. V-CS32 Valves: 8146 Normal Charging 8147 Alternate Charging Category: B Code Class: I Valves: 8378A Charging to Loop 3 Cold Leg Check 8378B Charging to Loop 4 Cold Leg Check 8379A Charging to Loop 3 Cold Leg Check 8379B Charging to Loop 4 Cold Leg Check Cateorv: C Code Class: I Valves: 8378B Charging Line Check Category: C Code Class: 2 Function:

These valves have active functions to open to supply normal and alternate charging to Loop 4 or 3 RCS Cold Legs.

Basis:

These valves should not be exercised during power operation because this would cause a thermal A.li transient to be induced on the charging to RCS Cold Leg nozzle. This is per Westinghouse Infogram (WIG)90-025.

Justification:

Cold shutdown frequency testing is per Part 10, paragraph 4.2.1.2(c) and 4.3.2.2(c).

10006620.1ST 40MIS 9g

-PACIFIC GAS & ELECTRIC COMPANY DIABLO CANYON POWER PLANT - UNITS I & 2 INSERVICE TESTING PROGRAM PLAN - PUMPS AND VALVES TABLE 2.1 ASME/ANSI OM-1987 (INCLUDING OMa-1988 ADDENDA) REV 20 (2003)

COLD SHUTDOWN FREQUENCY JUSTIFICATION PAGE 32 OF 33 NO. V-CS33 Valves: 8808A Si Accumulator I Discharge Isolation 8808B Si Accumulator 2 Discharge Isolation 8808C Si Accumulator 3 Discharge Isolation 8808D Si Accumulator 4 Discharge Isolation Category: B Code Class: 2 Function:

These valves are open with power removed from the valve operator during power operations. They are not required to operate during an accident requiring ECCS injection. Valves can be closed to prevent accumulator injection during normal cooldown/depressurization of RCS.

Basis:

These valves cannot be exercised during power operation because Technical Specification SR 3.5.1.1 and SR 3.5.1.5 require that accumulator discharge isolation valves remain open with power removed.

Justification:

Cold shutdown frequency testing is per Part 10, paragraph 4.2.1.2(c) and 4.3.2.2(c).

10006620.1ST 40MIS 100

PACIFIC GAS & ELECTRIC COMPANY .DIABLO CANYON POWER PLANT - UNITS I & 2 INSERVICE TESTING PROGRAM PLAN - PUMPS AND VALVES TABLE 2.1 ASME/ANSI OM-1987 (INCLUDING OMa-1988 ADDENDA) REV 20 (2003)

COLD SHUTDOWN FREQUENCY JUSTIFICATION PAGE 33 OF 33 NO. V-CS34 Valves: 8981 Refueling Water Storage Tank to Residual Heat Removal Pump Check Valve Categon: C Code Class: 2 Function:

This check valve has an active safety function o open to supply borated water from the RWST to the suction of the RHR pumps. This valve also has a safety function in the closed position (backflow) to limit potential post-LOCA recirculation leakage to the RWST.

Basis:

The valve cannot be full stroke exercised during power operation because the RHR pumps do not develop enough head to overcome RCS pressure.

The valve cannot be exercised during cold shutdown because both RHR pumps must be aligned to remove decay heat from the RCS; therefore no flow path exists for full stroke exercising the valve. The valve is not equipped with mechanical exercisers, position indicators or differential pressure instrumentation.

Valve 8981 will be full stroke exercised each refueling outage.

The valve can also be verified closed during cold shutdown by pressure testing the valve during plant cooldown. See refueling outage justification No. V-RO7.

Justification:

The valve shall be exercised to the closed position during cold shutdown per Part 10, paragraph 4.3.2.2(c).

10006620.1ST 40MIS 101

PACIFIC GAS & ELECTRIC COMPANY DIABLO CANYON POWER PLANT - UNITS &2 INSERVICE TESTING PROGRAM PLAN - PUMPS AND VALVES TABLE 2.2 ASMEIANSI OM-1987 (INCLUDING OMa-1988 ADDENDA) REV 20 (2003)

REFUELING OUTAGE FREQUENCY JUSTIFICATION PAGE I OF 21 NO. V-RO1 Valves: MS-1068, SteamGenerator#l MainSteamLineCheckValve MS-2066, Steam Generator #2 Main Steam Line Check Valve MS-3062, Steam Generator #3 Main Steam Line Check Valve MS-4062, Steam Generator #4 Main Steam Line Check Valve Catezory: C Code Class: N/IA Function:

These check valves have an active safety function to close in the event of a steam line break upstream of the main steam isolation valves. This accident mitigation function is to prevent the blowing down of more than one steam generator.

Basis:

These valves cannot be exercised closed because provisions are not provided in the plant design to verify that these valves close on reverse flow. Therefore, each refueling outage, these valves will be internally inspected using a fiberoptics scope to verify closure.

Justification:

Refueling outage frequency testing is per Part 10, paragraph 4.3.2.2(e).

Internal inspection using a fiberoptics scope is per Part 10, paragraph 4.3.2.4 (a), ("...other positive means.").

This is also supported by NRC Generic Letter 89-04, Attachment 1, position 3.

10006620.1ST 40MIS 102

PACIFIC GAS & ELECTRIC COMPANY DIABLO CANYON POWER PLANT - UNITS I & 2 INSERVICE TESTING PROGRAM PLAN - PUMPS AND VALVES TABLE 2.2 ASME/ANSI OM-1987 (INCLUDING OMa-1988 ADDENDA) REV 20 (2003)

REFUELING OUTAGE FREQUENCY JUSTIFICATION PAGE 2 OF 21 NO. V-RO2 Valves: 8475 Positive Displacement Charging Pump Discharge Check Valve 8478A Centrifugal Charging Pump # I Discharge Check Valve 8478B Centrifugal Charging Pump #2 Discharge Check Valve Category: C Code Class: 2 Function:

These valves have an active safety function to open to allow passage of their respective charging pump's discharge flow. They also have a safety function of preventing backflow from another charging pump while their respective pump is idle.

Basis:

8478A and 8478B cannot be full stroked open during power operation because of insufficient available flow.

These valves will be part stroke exercised during power operation.

8478A and 8478B cannot be full stroked open during cold shutdown because this could result in a possible low temperature overpressurization of the RCS. These valves will be full stroke exercised on the way to or during refueling outages.

Open stroke testing for 8475 will be performed quarterly.

All of these valves cannot be tested for backflow during power operation as the ory acceptable method of testing would be to perform hydros and measure for backleakage. This testing would require clearing pumps, entering ACTION statements, and numerous valve and pump manipulations rhich affect the pressurizer level control and letdown temperature. This can cause cavitation in the letdown line.

All of these valves cannot be tested for backflow during cold shutdown as the only acceptable method of testing would be to perform hydros and measure for backleakage. This testing would require clearing pumps, entering ACTION statements, and numerous valve and pump manipulations, along with setting up the hydro testing equipment. NUREG-1482, section 4.1.4, states that "the NRC has determined that the need to set up test equipment is adequate justification to defer backflow testing of a check valve until a refueling outage".

All three valves will be tested for backflow each refueling outage.

Justification:

Part stroke testing at power is per Part 10, paragraph 4.3.2.2(b).

Refueling outage frequency testing is per Part 10, paragraph 4.3.2.2(e).

10006620.1ST 40MIS 103

PACIFIC GAS & ELECTRIC COMPANY DIABLO CANYON POWER PLANT - UNITS I & 2 INSERVICE TESTING PROGRAM PLAN - PUMPS AND VALVES TABLE 2.2 ASMEIANSI OM-1987 (INCLUDING OMa-1988 ADDENDA) REV 20 (2003)

REFUELING OUTAGE FREQUENCY JUSTIFICATION PAGE 3 OF 21 NO. V-R03 Valves: 8804A, Charging Pump Suction from RHR System Isolation Valve 8804B, Safety Injection Pump Suction from RHR System Isolation Valve 9003A, RHR Hx- I to containment spray header A Isolation Valve 9003B, RHR Hx-2 to containment spray header A Isolation Valve Category: B Code Class: 2 Function:

These motor-operated gate valves have an active safety function to open. This will line up the safety injection system and the containment spray system for the cold leg recirculation phase of post-LOCA safety injection.

Basis:

These valves cannot be exercised during power operation because they are interlocked with valves 8982A&B (Containment Sump Isolation Valves) that are required to be closed with power to the valve operators removed by Technical Specification SR 3.5.2.1. Valves 8982A or B cannot be opened during power operation because this would result in one train of the RHR system being not OPERABLE.

During cold shutdown, valves 8804A & B and 9003A & B cannot be exercised open because they are interlocked with valve 8701 and 8702 (RCS Loop-4 TO RHR ISOLATION VALVES) in the closed position. 8701 and 8702 are required to be open and closing one of these valves would result in both RHR trains being incapable of removing decay heat from the core.

Valves 8804A&B and 9003A&B will be full stroke exercised during refueling outages.

Justification:

Refueling outage frequency testing is per Part 10, paragraph 4.2.1.2(e).

10006620.1ST 40MIS 104

PACIFIC GAS & ELECTRIC COMPANY DIABLO CANYON POWER PLANT - UNITS I & 2 INSERVICE TESTING PROGRAM PLAN - PUMPS AND VALVES TABLE 2.2 ASME/ANSI OM-1987 (INCLUDING OMa-1988 ADDENDA) REV 20 (2003)

REFUELING OUTAGE FREQUENCY JUSTIFICATION PAGE 4 OF 21 NO. V-RO4 Valves: 8819A, Safety Injection to Cold Leg #I Check Valve 8819B, Safety Injection to Cold Leg #2 Check Valve 8819C, Safety Injection to Cold Leg #3 Check Valve 8819D, Safety Injection to Cold Leg #4 Check Valve 8905A, Safety Injection to Hot Leg #I Check Valve 8905B, Safety Injection to Lot Leg #2 Check Valve 8905C, Safety Injection to Hot Leg #3 Check Valve 8905D, Safety Injection to Hot Leg #4 Check Valve Catezorv: AC Code Class: I Function:

These check valves have an active safety function to open to supply flow from the safety injection pumps to the reactor coolant system (RCS).

Basis:

These valves cannot be exercised during power operation because the safety injection pumps do not develop sufficient head to overcome RCS pressure.

These valves cannot be exercised during cold shutdown because a maximum of zero safety injection pumps are allowed to be capable of injecting into the RCS by Technical Specification SR 3.4.12.1 to protect against a low temperature overpressurization of the RCS. Also during cold shutdown there may not be sufficient volume in the RCS to accommodate the amount of water needed to full stroke exercise these valves.

These valves will be full stroke exercised during refueling outages.

Justification:

Refueling outage frequency testing is per Part 10, paragraphs 4.2.1.2(e) and 4.3.2.2(e).

10006620.1ST 40MIS 105

PACIFIC GAS & ELECTRIC COMPANY DIABLO CANYON POWER PLANT - UNITS I & 2 INSERVICE TESTING PROGRAM PLAN - PUMPS AND VALVES TABLE 2.2 ASMEtANSI OM-1987 (INCLUDING OMa-1988 ADDENDA) REV 20 (2003)

REFUELING OUTAGE FREQUENCY JUSTIFICATION PAGE 5 OF 21 NO. V-RO5 Valves: 8922A, Safety Injection Pump #I Discharge Check Valve 8922B, Safety Injection Pump #2 Discharge Check Valve Categorv: C Code Class: 2 Function:

These check valves have an active safety function to open to supply flow from the safety injection pumps to the reactor coolant system (RCS). They also have a closure safety function (backflow) to prevent pump to pump interaction.

Basis:

These valves cannot be exercised open during power operation because the safety injection pumps do not develop sufficient head to overcome RCS pressure.

These valves cannot be exercised open during cold shutdown because Technical Specification SR 3.4.12.1 requires that a maximum of zero safety injection pumps are capable of injecting into the RCS to protect against a low temperature overpressurization of the RCS. Also during cold shutdown there may not be sufficient volume in the RCS to accommodate the amount of water needed to full stroke exercise these valves.

These valves will be full stroked exercised open during refueling outages.

These valves will be tested for backflow quarterly.

Justification:

Refueling outage frequency testing is per Part 10, paragraph 4.3.2.2(e).

Ki' 10006620.1ST 40MIS 106

PACIFIC GAS & ELECTRIC COMPANY DIABLO CANYON POWER PLANT - UNITS &2 INSERVICE TESTING PROGRAM PLAN - PUMPS AND VALVES TABLE 2.2 ASME/ANSI OM-1987 (INCLUDING OMa-1988 ADDENDA) REV 20 (2003)

REFUELING OUTAGE FREQUENCY JUSTIFICATION PAGE 6 OF 21 NO. V-RO6 Valves: 8949A, Safety Injection to Hot Leg #1 Check Valve 8949B, Safety Injection to Hot Leg #2 Check Valve 8949C, Safety Injection to Hot Leg #3 Check Valve 8949D, Safety Injection to Hot Leg #4 Check Valve Category: AC Code Class: I Function:

These check valves have an active safety function to open to supply safety injection flow to the reactor coolant system (RCS) hot legs.

Basis:

Valves 8949A&B cannot be exercised during power operation because neither the residual heat removal nor the safety injection pumps develop sufficient head to overcome RCS pressure. Valves 8949C&D cannot be exercised during power operation because the safety injection pumps do not develop sufficient head to overcome RCS pressure.

These valves cannot be exercised during cold shutdown because a maximum of zero safety injection pumps are capable of injecting into the RCS by Technical Specification SR 3.4.12.1 to protect against a low temperature over-pressurization of the RCS. Valves 8949A&B cannot be exercised during cold shutdown using the RHR pump because this would result in short cycling the core and not removing decay heat

<_L properly.

These valves will be full stroke exercised during refueling outages.

Justification:

Refueling outage frequency testing is per Part 10, paragraphs 4.2.1.2(e) and 4.3.2.2(e).

10006620.1ST 40MIS 107

PACIFIC GAS & ELECTRIC COMPANY DIABLO CANYON POWER PLANT - UNITS &2 INSERVICE TESTING PROGRAM PLAN - PUMPS AND VALVES TABLE 2.2 ASME/ANSI OM-1987 (INCLUDING OMa-1988 ADDENDA) REV 20 (2003)

REFUELING OUTAGE FREQUENCY JUSTIFICATION PAGE 7 OF 21 NO. V-RO7 Valves: 8981 Refueling Water Storage Tank to Residual Heat Removal Pump Check Valve Category: C Code Class: 2 Function:

This check valve has an active safety function ;o open to supply borated water from the RWST to the suction of the RHR pumps. This valve also has a safety function in the closed position (backflow) to limit potential post-LOCA recirculation leakage to the RWST.

Basis:

The valve cannot be full stroked exercised during power operation because the RHR pumps do not develop enough head to overcome RCS pressure.

The valve cannot be exercised during cold shutdown because both RHR pumps must be aligned to remove decay heat from the RCS; therefore no flow path exists for full stroke exercising the valve. The valve is not equipped with mechanical exercisers, position indicators or differential pressure instrumentation.

Valve 8981 will be full stroke exercised each refueling outage.

The valve can be verified closed during cold shutdown by pressure testing the valve during plant cooldown.

See cold shutdown justification No. V-CS34.

Justification:

The valve shall be full stroke exercised during refueling outages per Part 10, paragraph 4.3.2.2(e).

10006620.1ST 40MIS 108

PACIFIC GAS & ELECTRIC COMPANY DIABLO CANYON POWER PLANT - UNITS I &

INSERVICE TESTING PROGRAM PLAN - PUMPS AND VALVES TABLE 2.2 ASME/ANSI OM-1987 (INCLUDING OMa-1988 ADDENDA) REV 20 (2003)

REFUELING OUTAGE FREQUENCY JUSTIFICATION PAGE 8 OF 21 NO. V-R08 Valves: 8982A, Containment Recirc Sump to RHR Pump # 1 Isolation Valve (Outside Containment) 8982B, Containment Recirc Sump to RHR Pump #2 Isolation Valve (Outside Containment)

Categomm B Code Class: 2 Function:

These motor-operated gate valves have an active safety function to open which allows the RHR pumps to take suction from the containment recirculation sumpsduring the cold leg recirculation phase of an accident.

Basis:

These valves cannot be exercised during power operation because they are required to be closed with power to the valve operators removed by Technical Specification SR 3.5.2.1. If these valves were opened during power operation, this would result in one train of the RHR system being not OPERABLE.

These valves cannot be exercised during cold shutdown because opening one of these valves could introduce air into the suction piping of the RHR pumps, causing the RHR pumps to be not OPERABLE for an extended period of time.

These valves will be full stroke exercised on a refueling outage frequency.

Justification:

Refueling outage frequency testing is per Part 10, paragraph 4.2.1.2(e).

10006620.1ST 40MIS 109

PACIFIC GAS & ELECTRIC COMPANY DIABLO CANYON POWER PLANT - UNITS &2 INSERVICE TESTING PROGRAM PLAN - PUMPS AND VALVES TABLE 2.2 ASME/ANSI OM-1987 (INCLUDING OMa-1988 ADDENDA) REV 20 (2003)

REFUELING OUTAGE FREQUENCY JUSTIFICATION PAGE 9 OF 21 NO. V-Ro9 Valves: 8820, Charging Injection 2nd-off Check Valve 8900A, Charging Injection Loop- I Cold Leg Check Valve 8900B, Charging Injection Loop-2 Cold Leg Check Valve 8900C, Charging Injection Loop-3 Cold Leg Check Valve 8900D, Charging Injection Loop-4 Cold Leg Check Valve Caterory: C Code Class: I Function:

These check valves have an active safety function to open to supply safety injection flow to the reactor coolant system (RCS) cold legs from the high-head safety injection pumps (centrifugal charging pumps).

Basis:

These valves cannot be full stroke exercised during plant operation because the high RCS pressure will prevent the maximum required injection flow rate. Part stroke exercising these valves during plant operation is not practicable because any flow through the valves would result in unnecessary thermal transients on the RCS cold leg nozzles.

These valves cannot be full stroke exercised during cold shutdown because of insufficient RCS expansion volume to accommodate the high flow rates required to full stroke these valves. These high flow rates could challenge the RCS low temperature overpressure (LTOP) mitigation system. To prevent challenging the LTOP system, venting of the pressurizer by removal of a safety valve would be required. Additionally, full stroke exercising these valves cannot be performed with a bubble in the pressurizer, because the net charging rate must be minimal to prevent thermal cycling of the pressurizer.

Valves 8900A-D cannot be part stroke exercised during cold shutdown for the same reasons that they cannot be full stroked. In addition, the charging injection flow path is not designed for throttled operation which would be required to part stroke all four parallel check valves.

These valves are not equipped with mechanical exercisers, position indicators, or differential pressure instrumentation.

These valves will be full stroke exercised on a refueling outage frequency. In addition, valve 8820 will be part stroked during cold shutdowns via a small test line.

Justification:

Part-stroking during cold shutdown is per Part 10, paragraph 4.3.2.2(d).

Refueling outage frequency testing is per Part 10, paragraph 4.3.2.2(e).

10006620.1ST 40MIS 110

PACIFIC GAS & ELECTRIC COMPANY DIABLO CANYON POWER PLANT - UNITS &

INSERVICE TESTING PROGRAM PLAN - PUMPS AND VALVES TABLE 2.2 ASME/ANSI OM-1987 (INCLUDING OMa-1988 ADDENDA) REV 20 (2003)

REFUELING OUTAGE FREQUENCY JUSTIFICATION PAGE 10 OF 21 NO. V-ROIO Valves: SW-34, ASW Pump #I Discharge Line Vacuum Relief Check SW- 70, ASW Pump #I Discharge Line Vacuum Relief Check SW-301, ASW Pump #2 Discharge Line Vacuum Relief Check SW-303, ASW Pump #2 Discharge Line Vacuum Relief Check Catezorv: C Code Class: 3 Function:

These check valves have a safety related function in the open direction to serve as vacuum relief valves for the Auxiliary Saltwater System (ASW) pumps' discharge lines. Within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after a LOCA. the two ASW trains are isolated from each other. If an ASW pump is stopped and later restarted in this situation, then these check valves must open to permit the passage of air into the discharge line while the pump is shut down in order to prevent water hammer and resultant damage in the line and in the CCW heat exchanger, when the pump is restarted.

The check valves have the safety related functions in the closed direction (backflow) of preventing ASW flow out the vent, and maintaining the pressure boundary integrity of the ASW system.

Basis:

These valves are disassembled and inspected on a refueling outage fiequency in accordance with Part I0, paragraph 43.2.4(c).- This will prove both the open and close functions.

Justification:

Part 10, paragraph 4.3.2.4(c). (Refueling outage justification not required.)

10006620.1ST 4OMIS IXI

PACIFIC GAS & ELECTRIC COMPANY DIABLO CANYON POWER PLANT - UNITS I &

INSERVICE TESTING PROGRAM PLAN - PUMPS AND VALVES TABLE 2.2 ASME/ANSI OM-1987 (INCLUDING OMa-1988 ADDENDA) REV 20 (2003)

REFUELING OUTAGE FREQUENCY JUSTIFICATION PAGE 11 OF 21 NO. V-RO11 Valves: 8440 Volume Control Tank Outlet Check Valve Category: C Code Class: 2 Function:

This check valve has an active safety function to close to prevent backflow from the charging pump suction header to relief valve 8123 during the post-LO'A containment sump recirculation mode of safety injection.

It also has a safety function to open to provide a flow path for the charging pump mini-flow recirculation to return to the suction header of the charging pumps.

Basis:

This check valve is open during operation to provide the normal source of supply to the suction of the charging pumps. Exercising this valve during power operation would require alignment to the alternate supply which would result in injecting highly oxygenated, 2000 ppm borated water into the reactor coolant system. Injecting this water results in a negative reactivity addition to the reactor coolant system which could shut the plant down.

This valve cannot be tested for backflow during power operation as the only acceptable method of testing would be to perform hydros and measure for backleakage. This testing would require clearing pumps, entering ACTION Statements, and numerous valve and pump manipulations which affect the pressurizer level control and letdown temperature. This can cause cavitation in the letdown line.

This valve cannot be tested for backflow during cold shutdown as the only acceptable method of testing would be to perform hydros and measure for backleakage. This testing would require clearing pumps, entering ACTION Statements, and numerous valve and pump manipulations along with setting up the hydro testing equipment. NUREG-1482, Section 4.1.4, states that "the NRC has determined that the need to set up test equipment is adequate justification to defer backflow testing of a check valve until a refueling outage."

The ability to open is proven during normal operations per section 4.2.1.5. Closure will be tested on a refueling outage frequency.

Justification:

Refueling outage frequency testing is per Part 10, paragraph 4.3.2.2(e).

10006620.1ST 40MIS 112

PACIFIC GAS & ELECTRIC COMPANY DIABLO CANYON POWER PLANT - UNITS I & 2 INSERVICE TESTING PROGRAM PLAN - PUMPS AND VALVES TABLE 2.2 ASME/ANSI OM-1987 (INCLUDING OMa-1988 ADDENDA) REV 20 (2003)

REFUELING OUTAGE FREQUENCY JUSTIFICATION PAGE 12 OF 21 NO. V-RO12 Valves: RHR-8740A, RHR to Hot Leg #1 Check Valve RHR-8740B, RHR to Hot Leg #2 Check Valve Category: AC Code Class: I Function:

These valves have an active safety function to open to supply RHR flow to RCS Hot Legs I and 2.

Basis:

These valves cannot be exercised during power operation because the RHR Pumps do not develop sufficient head to overcome RCS pressure.

These valves cannot be exercised during cold shutdown because due to lack of instrumentation necessary to individually verify full stroke capability of each valve.

These valves are not equipped with mechanical exercisers, position indicators or differential pressure instrumentation.

These valves will be full stroked open on a refueling outage frequency.

If any degradation is detected that interferes with a valve's operability then the valve will be disassembled, internally inspected, and manually full stroke exercised during the same outage.

K., Justification:

Refueling outage frequency testing is per Part 10, paragraph 4.3.2.2(e).

10006620.1ST 40MIS 113

PACIFIC GAS & ELECTRIC COMPANY DIABLO CANYON POWER PLANT - UNITS I & 2 INSERVICE TESTING PROGRAM PLAN - PUMPS AND VALVES TABLE 2.2 K> ASME/ANSI OM- 1987 (INCLUDING OMa-1988 ADDENDA) REV 20 (2003)

REFUELING OUTAGE FREQUENCY JUSTIFICATION PAGE 13 OF 21 NO. V.-RO13 Valves: 881 SA, RHR to Cold Leg # I Check Valve 881 8B, RHR to Cold Leg #2 Check Valve 881 8C, RHR to Cold Leg #3 Check Valve 881 8D, RHR to Cold Leg #4 Check Valve Category: AC Code Class: I Function:

These valves have an active safety function to open to supply RHR flow to RCS Cold Legs 1,2, 3 and 4.

Basis:

These valves cannot be exercised during power operation because the RHR Pumps do not develop sufficient head to overcome RCS pressure.

These valves cannot be exercised during cold shutdown because due to lack of instrumentation necessary to individually verify full stroke capability of each valve.

These valves are not equipped with mechanical exercisers, position indicators or differential pressure instrumentation.

These valves will be non-intrusively tested (NIT) on a refueling outage frequency.

If any degradation is detected that interferes with a valve's operability then the valve will be disassembled, internally inspected, and manually full stroke exercised during the same outage.

Justification:

Refueling outage frequency testing is per Part 10, paragraph 4.3.2.2(e).

10006620.1ST 40MIS 114

PACIFIC GAS & ELECTRIC COMPANY DIABLO CANYON POWER PLANT - UNITS I & 2 INSERVICE TESTING PROGRAM PLAN - PUMPS AND VALVES TABLE 2.2 ASME/ANSI OM-1987 (INCLUDING OMa-1988 ADDENDA) REV 20 (2003)

REFUELING OUTAGE FREQUENCY JUSTIFICATION PAGE 14 OF 21 NO. V-RO14 Valves: RCS-508, Relief Valve and Stem Leak Off Header to PRT Check Valve RCS-8028, Relief Valve Discharge Header to PRT Isolation Inside Containment Category: RCS-8028 AC Code Class: 2 Catecory: RCS-508 C Code Class: 3 Function:

These valves have an active safety function to open to provide flow path for relief valves' discharge to PRT.

RCS-8028 also has an active safety function to close to provide containment isolation.

Basis:

These valves cannot be full or part stroke exercised during power operation because the relief valve header is required to be in service during power operation. Test method employed to close stroke test RCS-802 is local leak rate test which isolates the relief valve header from the relief valves.

These valves cannot be part or full stroke exercised during cold shutdown because the relief valve header is required to be in service.

These valves are not equipped with mechanical exercisers, position indicators or differential presstre instrumentation.

These valves will be disassembled and manually exercised on a refueling outage frequency.

Justification:

Refueling outage frequency testing is per Part 10, paragraph 4.3.2.2(e).

10006620.1ST 40MIS 115

PACIFIC GAS & ELECTRIC COMPANY DIABLO CANYON POWER PLANT - UNITS I & 2 INSERVICE TESTING PROGRAM PLAN - PUMPS AND VALVES TABLE 2.2 ASME/ANSI OM-1987 (INCLUDING OMa-1988 ADDENDA) REV 20 (2003)

REFUELING OUTAGE FREQUENCY JUSTIFICATION PAGE 15 OF 21 NO. V-RO15 Valves: CCW-581, FCV-749 Bypass Check Valve CCW-670, FCV-750 Bypass Check Valve CVCS-8109, 8112 Bypass Check Valve Category: A,C Code Class: 2 Function:

The Bypass Check Valves have a safety function to open to relieve pressure buildup in Containment Penetrations 20, 21 and 45 when the containment penetration is isolated. They also serve as containment isolation valves, so they have a safety function in the closed direction (this function is already included on V-RR2 for valve 8109)..

Basis:

These Bypass Check Valves cannot be exercised during power operation because the test would require clearing the reactor coolant pumps which are required for power operations. The tests also require that test equipment be set up inside the containment building.

These valves cannot be tested during cold shutdown because the test requires setting up test equipment inside containment, clearing reactor coolant pumps, and numerous valve manipulations.

These valves are not equipped with mechanical exercisers, position indicators or differential pressure instrumentation.

Justification:

Refueling outage frequency testing is per Part 10, paragraph 4.3.2.2(e), and verifying closure by leak testing is preapproved per NUREG- 1482, Section 4.1.4.

10006620.1ST 40MIS 116

PACIFIC GAS & ELECTRIC COMPANY DIABLO CANYON POWER PLANT - UNITS I & 2 INSERVICE TESTING PROGRAM PLAN - PUMPS AND VALVES TABLE 2.2 ASME/ANSI OM-1987 (INCLUDING OMa-1988 ADDENDA) REV 20 (2003)

REFUELING OUTAGE FREQUENCY JUSTIFICATION PAGE 16 OF 21 NO. V-RO16 Valves: CCW-4, Suction Cross-tie Valve between CCW Headers B&C CCW-5, Suction Cross-tie Valve between CCW Headers A&C Category: B Code Class: 3 Function:

These valves perform an active safety function in that they are manually closed to provide CCW train separation in Emergency Operating Procedures.

Basis:

These normally sealed open manual valves cannot be exercised during power operation because closing them would isolate the suction side of two CCW Pumps from one of the vital CCW Headers. UFSAR Table 9.2-7 lists the failure of a CCW Pump to start as one of the malfunctions analyzed by the SAR. The closure of manual valve CCW4 in conjunction with a failure of CCW Pump 1 to start would cause CCW Header B to be inoperable. The closure of CCW-5 in conjunction with the failure of CCWpump 3 to start would result in an inoperable CCW Header A.

Closure of these CCW Suction Header Cross-tie valves could also result in perturbations in CCW flow because return header flows are not equal and some flow through the suction cross-ties is needed during normal operations. These perturbations could adversely impact the ability of the CCW System to remove heat from various loads and are sufficient reason to not perform valve testing during transient plant conditions (i.e., forced outages).

Since these manual valves have very few failure mechanisms as opposed to power operated valves which have more failure mechanisms the risk of performing this test is not offset by the benefits of testing the valve and possibly identifying failure or degraded condition. The valves will be part stroke tested Quarterly and full stroke tested on a refueling outage frequency. The code committee is considering a five year frequency test for manual valves, so this is an indication of how much benefit there is to testing manual valves.

These manual valves cannot be stroked during Cold Shutdown because CCW is required to cool Residual Heat Removal System Heat Exchangers during cold shutdown, especially during the first few days of cold shutdown. The test would require splitting CCW Headers by manipulating several sealed open manual valves and aligning CCW into an abnormal system alignment.

Full stroke of these manual valves will be tested on a refueling outage frequency.

Justification:

Refueling outage frequency testing is per Part 0, paragraph 4.2.1.2(e).

10006620.1ST 40MIS 117

PACIFIC GAS & ELECTRC COMPANY DIABLO CANYON POWER PLANT - UNITS I & 2 INSERVICE TESTING PROGRAM PLAN - PUMPS AND VALVES TABLE 2.2 K> ASME/ANSI OM-1987 (INCLUDING OMa-1988 ADDENDA) REV 20 (2003)

REFUELING OUTAGE FREQUENCY JUSTIFICATION PAGE 17 OF 21 NO. V-RO17 Valves: 8483, Charging Flow to Cold Legs Bypass Check Valve Category: C Code Class: I Function:

This valve has a safety function to open to relieve pressure build up if normal and alternate charging valves 8146 and 8147 are both closed and Regenerath.e Heat Exchanger added heat to the charging line with resulting thermal expansion and pressure increase. The valve need only to partially open and allow flow to perform its safety function.

Basis:

This check valve cannot be exercised during power operation because opening this valve would require closing normal and alternate charging valves 8146 and 8147 which would isolate normal charging. This would result in thermal transient to be induced in the charging to RCS Cold Leg nozzles. This is per Westinghouse Infogram (WIG 90-025).

This valve cannot be tested for flow during Cold Shutdown as the only acceptable method of testing is to isolate normal and alternate charging thus isolating charging flow. The resultant differential pressure seen by 8146 or 8147 would be extremely high because all of the charging pump pressure would have to be reduced at the normal or alternate charging valve which is not set up to accomplish this. The valve can be tested during refueling outages when charging pump full flow tests using charging injection flow path are performed. During the charging pump full flow tests, the pressures differential across the normal or alternate charging valves is much lower.

Justification:

Refueling outage frequency testing is per Part 10, paragraph 4.3.2.2(e).

10006620.1ST 40MIS 118

PACIFIC GAS & ELECTRC COMPANY DIABLO CANYON POWER PLANT - UNITS I & 2 INSERVICE TESTING PROGRAM PLAN - PUMPS AND VALVES TABLE 2.2 ASME/ANSI OM-1987 (INCLUDING OMa-1988 ADDENDA) REV 20 (2003)

REFUELING OUTAGE FREQUENCY JUSTIFICATION PAGE 18 OF 21 NO. V-R018 Valves: VAC-252, Containment Hydrogen Sample Return Isolation Check Valve (IC)

VAC-253, Containment Hydrogen Sample Return Isolation Check Valve (IC)

Categorv: A, C Code Class: 2 Function:

These valves have a safety function supporting the containment hydrogen monitoring capability by opening to complete the sample flow path from the containment, through the hydrogen monitor, and back to the containment. They also have a safety function in the closed direction of preventing back leakage to maintain design basis containment integrity.

Basis:

These check valves cannot be exercised during power operation because Technical Specification SR 3.6.3.3 and SR 3.6.3.4 require the Containment H2 Sample Supply and Return Isolation Valves to be closed when containment integrity is required. These valves do not receive a containment isolation signal. No other practical way of flow testing the check valves is available without opening of the Containment H2 Sample Supply and Return Isolation Valves.

Theses check valves can be partial stroke tested during Cold Shutdown by operation of the containment hydrogen monitors. Flow is provided by the H2 monitor sample pumps, which are aligned to the check valves. However, since the only available flow meter in this path is an uncalibrated rotameter full design flow through the check valves cannot be verified.

Therefore, each refueling outage, these valves will be full stroked exercised by flowing air through them and measuring the air flow using a calibrated flow instrument. Since this test involves setting up of temporary test equipment inside the containment it is impractical to perform this during Cold Shutdown.

The basis for the refueling outage frequency for the closed stroke test is explained in Request for Relief No.

V-RR2.

Justification:

Refueling outage frequency testing is per Part 10, paragraph 4.3.2.2(d).

10006620.1ST 40MIS 119

PACIFIC GAS & ELECTRIC COMPANY DIABLO CANYON POWER PLANT - UNITS I & 2 INSERVICE TESTING PROGRAM PLAN - PUMPS AND VALVES TABLE 2.2 ASME/ANSI OM-1987 (INCLUDING OMa-1988 ADDENDA) REV 20 (2003)

REFUELING OUTAGE FREQUENCY JUSTIFICATION PAGE 19 OF 21 NO. V-RO19 Valves: 8977 RWST to Safety Injection Pump Check Valve Category: C Code Class: 2 Function:

This check valve has an active safety function to open to supply borated water from the RWST to the suction of the Safety Injection Pumps. This valve alsc has a safety function in the closed position (backflow) to limit potential post-LOCA recirculation leakage to the RWST.

Basis:

The valve cannot be full stroked exercised during power operation because the Safety Injection Pumps do not develop enough head to overcome RCS pressure.

The valve cannot be exercised during cold shutdown because a maximum of zero Safety Injection Pumps are allowed to be capable of injecting into the RCS per Technical Specification SR 3.4.12.1 to protect against a low temperature over pressurization of the RCS.

Close exercising of valve 8977 is not practicable during power operation or cold shutdown because the test method used would require either the use of a hydro pump to pressurize the suction side of the safety injection pumps or opening of SI-8804B to pressurize the suction of the safety injection pumps using an RHR pump, neither of which can be performed when the plant is in cold shutdown. The valve is not Y_,f equipped with mechanical exercisers, position indicators or differential pressure instrumentation.

Valve 8977 can be part stroke tested open quarterly and full stroke tested each refueling outage.

Justification:

The valve shall be part stroke exercised quarterly and full stroke exercised during refueling outages per Part 10, paragraph 4.3.2.2(b/d).

10006620.1ST 40MIS 120

PACIFIC GAS & ELECTRIC COMPANY DIABLO CANYON POWER PLANT - UNITS &

INSERVICE TESTING PROGRAM PLAN - PUMPS AND VALVES TABLE 2.2 ASME/ANSI OM-1987 (INCLUDING OMa-1988 ADDENDA) REV 20 (2003)

REFUELING OUTAGE FREQUENCY JUSTIFICATION PAGE 20 OF 21 NO. V-RO20 Valves: 8924 RWST to Charging Pump Check Valve Category: C Code Class: 2 Function:

This check valve has an active safety function to open to supply borated water from the RWST to the suction of the Charging Pumps. This valve also has a safety function in the closed position (backflow) to limit potential post-LOCA recirculation leakage to the RWST.

Basis:

The valve cannot be full stroked exercised during power operation because this would require injecting borated water from the RWST into the RCS, which could result in a plant shutdown.

The valve cannot be exercised during cold shutdown because of the high flow rates could challenge the RCS low temperature overpressure protection system.

Close exercising of valve 8924 is not practicable during power operation or cold shutdown because the test method used would require either the use of a hydro pump to pressurize the suction side of the charging pumps or opening of SI-8804A to pressurize the suction of the charging pumps using an RHR pump, neither of which can be performed when the plant is in cold shutdown. The valve is not equipped with mechanical exercisers, position indicators or differential pressure instrumentation.

Valve 8924 can be part stroke tested open during cold shutdown and full stroke tested each refueling outage.

Justification:

The valve shall be part stroke exercised during cold shutdowns and full stroke exercised during refueling outages per Part 10, paragraph 4.3.2.2(d) and 4.3.2.2(e).

10006620.1ST 40MIS 121

PACIFIC GAS & ELECTRIC COMPANY DIABLO CANYON POWER PLANT - UNITS I & 2 INSERVICE TESTING PROGRAM PLAN - PUMPS AND VALVES TABLE 2.2 ASME/ANSI OM-1987 (INCLUDING OMa-1988 ADDENDA) REV 20 (2003)

REFUELING OUTAGE FREQUENCY JUSTIFICATION PAGE 21-OF 21 NO. V-RO21 Valves: 8078A Reactor Vessel Head Vent Valve 8078B Reactor Vessel Head Vent Valve 8078C Reactor Vessel Head Vent Valve 8078D Reactor Vessel Head Vent Valve Categorv: B Code Class: 2 Function:

These valves have an active function to open to vent noncondensible gases from the RCS, which might inhibit core cooling during natural circulation. They were installed to provide reactor vessel high point vent capability for beyond-design-bases events per the guidance of NUREG 0737 and are not relied upon to mitigate any design basis accidents as defined and analyzed in the FSAR Chapter 15 Accident Analyses.

Basis:

These Reactor Vessel Head Vent Valves should not be exercised during power operation by NRC direction.

Stroke time testing of the Reactor Vessel Head Vent Valves during Cold Shutdown has resulted in borated water fiom the valves to drip onto the Reactor Vessel Head. The borated water could cause corrosion damage to the Reactor Vessel Head. During Refueling Outages special test equipment is set up inside the

• Containment Building to flush the Reactor Vessel Head Vent Valves and piping with demineralized water after the stroke tests are complete. Setting up the special test equipment inside containment is impractical during Cold Shutdown forced outages, because the Reactor Vessel head is inaccessible and there would be significant radiation exposure to personnel.

Justification:

Refueling Outage frequency testing per Part 10, paragraph 4.3.2.2(e).

10006620.1ST 40MIS 122

PACIFC GAS & ELECTRIC COMPANY C DIABLO CANYON POWER PLANT - UNITS I & 2 INSERVICE TESTING PROGRAM PLAN - PUMPS AND VALVES TABLE 2.3 ASME/ANSI OM-1987 (INCLUDING OMa-1988 ADDENDA) REV 20 (2003)

REQUESTS FOR RELIEF FROM CODE REQUIREMENTS PAGE I OF 9 I Lry 1:1-REQUEST COMPONENT RELIEF REQUEST APPROVAL STATUS I Auxiliary Feedwater Pump suction check valves:

FW-349, FW-353 Preapproved per GL 89-04, Attach 1, position 2.

2 Category A/C check valves:

AIR-I-587, CCW-585, CCW-695, LWS-60, VAC-21, VAC-1 16, VAC-252, VAC-253, 8046, 8047, 8109, 8368A, 8368B, 8368C, 8368D, 8916 Preapproved per NUREG- 1482, section 4.1.4 3

4 Deleted, see Refueling Justification # V-RO20 Safety injection cold leg check valves:

-I 8948A, 8948B, 8948C, 8948D Preapproved per NUREG-1482, section 4.1.2 5 Accumulator discharge check valves:

8956A, 8956B, 8956C, 8956D Preapproved per NUREG- 1482, section 4.1.2 6 Deleted, see Refueling Justification # V-ROI 9 7 Deleted, See Reffieling Justification #V-RO12 Containment spray ring header check valves:

9011 A, 9011 B Preapproved per GL 89-04, Attach 1, position 2 9 Deleted, See Refueling Justification #V-RO1 3 10 Containment spray pump discharge check valves:

9002A, 9002B Preapproved per NUREG- 1482, section 4.1.2 I

10006620.1ST 40MIS 123

PACIFIC GAS & ELECTRIC COMPANY DIABLO CANYON POWER PLANT NITS I & 2

(..

INSEKF-E TESTING PROGRAM PLAN - PUMPS AND VALVES TABLE 2.3 ASME/ANSI OM-1987 (INCLUDING OMa-1988 ADDENDA) REV 20 (2003)

REQUESTS FOR RELIEF FROM CODE REQUIREMENTS PAGE2OF9 RELIEF REQUEST COMPONENT RELIEF REQUEST APPROVAL STATUS 11 AFW Pump steam supply check valves:

MS-5166, MS-5167 Preapproved per GL 89-04, Attach I, position 2 10006620.1ST 40MIS 124

PACIFIC GAS & ELECTRIC COMPANY DIABLO CANYON POWER PLANT - UNITS I & 2 INSERVICE TESTING PROGRAM PLAN - PUMPS AND VALVES TABLE 2.3 ASME/ANSI OM-1987 (INCLUDING OMa-1988 ADDENDA) REV 20 (2003)

REQUESTS FOR RELIEF FROM CODE REQUIREMENTS PAGE 3 OF 9 NO. V-RR1 Valves: FW-349, Aux Feedwater Pump #1 Suction Check from the Raw Water Storage Reservoir FW-353, Aux Feedwater Pump #2 & #3 Suction Check from the Raw Water Storage Reservoir Category: C Code Class: 3 Test Reot: Part 10 does not provide for sampling.

Function:

These check valves have an active safety function to open to supply an additional source of water to the steam generators via the auxiliary feedwater pumps.

Basis:

These valves cannot be exercised with flow because the water from the Raw Water Storage Reservoir would contaminate the steam generators creating chemistry problems which could effect the integrity of the steam generator tubes.

These valves are not equipped with mechanical exercisers, position indicators or differential pressure instrumentation.

These valves will be disassembled, internally inspected, and manually full stroke exercised on a rotational basis, one valve each refueling outage. If any degradation is detected that interferes with the valve's operability, then the opposite train valve will also be disassembled, internally inspected, and manual full stroke exercised during the same outage.

Justification:

Disassembly and inspection each refueling outage is per Part 10, paragraph 4.3.2.4(c).

Disassembly and inspection sampling program is preapproved per NRC Generic Letter 89-04, , position 2.

10006620.1ST 40MIS 125

PACIFIC GAS & ELECTRIC COMPANY DIABLO CANYON POWER PLANT - UNITS I & 2 INSERVICE TESTING PROGRAM PLAN - PUMPS AND VALVES TABLE 2.3 ASME/ANSI OM-1987 (INCLUDING OMa-1988 ADDENDA) REV 20 (2003)

REQUESTS FOR RELIEF FROM CODE REQUIREMENTS PAGE 4 OF 9 NO. V-RR2 Valves: AIR-1-587 Containment Normal Instrument Air Supply Isolation Check (OC)

CCW-585 CCW to RCP & Reactor Vessel Support Isolation Check (IC)

CCW-695 CCW to Excess Letdown Heat Exchanger Isolation Check (OC)

LWS-60 Nitrogen to RCDT Isolation Check (IC)

VAC-21 Containment Air Sample Return Isolation Check (IC)

VAC- 116 Containment Air Sample Post-LOCA Return Isolation (IC)

VAC-252 Containment Hydrogen Sample Return Isolation Check (IC)

VAC-253 Containment Hydrogen Sample Return Isolation Check (IC) 8046 Primary Water to PRT Isolation Check (IC) 8047 Nitrogen to PRT Isolation Check (IC) 8109 RCP Seal Water Return Isolation Check (IC) 8368A RCP-l Seal Injection Isolation Check (IC) 8368B RCP-2 Seal Injection Isolation Check (IC) 8368C RCP-3 Seal Injection Isolation Check (IC) 8368D RCP-4 Seal Injection Isolation Check (IC) 8916 Nitrogen Supply to Accumulator Isolation Check (IC)

Category: AC Code Class: 2 Test Rent: Part 10, section 4.3.2.1, "Exercising Test Frequency".

Function:

These check valves have the safety function to prevent reverse flow from containment to the system outside of containment.

Basis:

These check valves can only be verified closed by leakrate testing. They will be leakrate tested each refueling outage.

Justification:

Extension of test interval to refueling outage for check valves verified closed by leak testing is preapproved per NUREG- 1482, section 4.1.4.

10006620.1ST 4OMIS 126

PACIFIC GAS & ELECTRIC COMPANY DIABLO CANYON POWER PLANT - UNITS I & 2 INSERVICE TESTING PROGRAM PLAN - PUMPS AND VALVES TABLE 2.3 ASME/ANSI OM-1987 (INCLUDING OMa-1988 ADDENDA) REV 20 (2003)

REQUESTS FOR RELIEF FROM CODE REQUIREMENTS PAGE S OF 9 NO. V-RR4 Valves: 8948A Safety Injection to Cold Leg # I Check Valve 8948B Safety Injection to Cold Leg #2 Check Valve 8948C Safety Injection to Cold Leg #3 Check Valve 8948D Safety Injection to Cold Leg #4 Check Valve Category: AC Code Class:

Test Rent: Part 10 does not provide for sampling.

Function:

These check valves have an active safety function to open to supply safety injection flow to the RCS cold legs.

Basis:

These valves cannot be exercised during power operation because the accumulators, RHR pumps, and S1 pumps do not develop sufficient head to overcome RCS pressure.

These valves cannot be tested during cold shutdown due to lack of instrumentation necessary to individually verify full stroke capability of each valve.

These valves are not equipped with mechanical exercisers, position indicators or differential pressure instrumentation.

These valves will be non-intrusively tested (NIT), on a sampling program, per NUREG-1482. This program will NIT one valve each refueling outage, on a rotating schedule, while partial flow testing the other three valves.

If any degradation is detected that interferes with a valve's operability then the valve will be disassembled, internally inspected, and manually full stroke exercised during the same outage. In addition, the other three valves in this group will be NIT during the same outage.

Justification:

Preapproved per NUREG-1482, section 4.1.2.

10006620.1ST 40MIS 127

PACIFIC GAS & ELECTRC COMPANY DIABLO CANYON POWER PLANT - UNITS I & 2-INSERVICE TESTING PROGRAM PLAN - PUMPS AND VALVES TABLE 2.3 ASMEIANSI OM-1987 (INCLUDING OMa-1988 ADDENDA) REV 20 (2003)

REQUESTS FOR RELIEF FROM CODE REQUIREMENTS PAGE 6 OF 9 NO. V-RR5 Valves: 8956A Accumulator#1 Discharge Check Valve 8956B Accumulator #2 Discharge Check Valve 8956C Accumulator #3 Discharge Check Valve 8956D Accumulator #4 Discharge Check Valve Category: AC Code Class: I Test Reqt: Part 10 does not provide for sampling.

Function:

These check valves have an active safety function to open to supply flow from the accumulators to the RCS during an accident condition. They also have a passive safety function to prevent backflow from the RCS into the accumulators during normal operations.

Basis:

These valves cannot be exercised during power operation because the accumulators cannot overcome RCS pressure.

These valves cannot be exercised during cold shutdowns because this could result in a possible low temperature overpressurization of the RCS.

Full flow testing of these valves during refueling outages is not feasible because of the resulting water surge into the reactor vessel and potential for high airborne radiation problems.

These valves are not equipped with mechanical exercisers, position indicators or differential pressure instrumentation.

These valves will be non-intrusively tested (NIT), on a sampling program, per NUREG- 1482. This program will NIT one valve each refueling outage, on a rotating schedule, while partial flow testing the other three valves.

If any degradation is detected that interferes with a valve's operability then the valve will be disassembled, internally inspected, and manually full stroke exercised during the same outage. In addition, the other three valves in this group will be NIT during the same outage.

Justification Preapproved per NUREG-1482, section 4.1.2.

10006620.1ST 40MIS 128

PACIFIC GAS & ELECTRIC COMPANY DIABLO CANYON POWER PLANT - UNITS 1 & 2 INSERVICE TESTING PROGRAM PLAN - PUMPS AND VALVES TABLE 2.3 ASME/ANSI OM-1987 (INCLUDING OMa-1988 ADDENDA) REV 20 (2003)

REQUESTS FOR RELIEF FROM CODE REQUIREMENTS PAGE 7 OF 9 NO. V-RR8 Valves: 901 IA, Containment Spray Header A Isolation Check Valve (IC) 901 1B, Containment Spray Header B Isolation Check Valve (IC)

Category: AC Code Class: 2 Test Rejt: Part 10 does not provide for sampling.

Function:

These check valves have an active safety function to open to allow full containment spray flow following an accident. They also have a safety function in the closed position (back leakage) to provide containment isolation.

Basis:

These valves cannot be exercised during power operations, cold shutdown, or refueling outages because flow through these valves would result in spraying containment.

These valves are not equipped with mechanical exercisers, position indicators or differential pressure instrumentation.

These valves will be disassembled, internally inspected, and manually full stroke exercised on a rotational basis, one valve each refueling outage. If any degradation is detected that interferes with the valves operability, then the opposite train valve will also be disassembled, internally inspected, and manual full stroke exercised during the same outage.

Justification:

Disassembly and inspection each refueling outage is per Part 10, paragraph 4.3.2A(c).

Disassembly and inspection sampling program is preapproved per NRC Generic Letter 89-04, , position 2.

10006620.1ST 40MIS 129 '

I PACIFIC GAS & ELECTRC COMPANY DIABLO CANYON POWER PLANT - UNITS I & 2 INSERVICE TESTING PROGRAM PLAN - PUMPS AND VALVES TABLE 2.3 ASME/ANSI OM-1987 (INCLUDING OMa-1988 ADDENDA) REV 20 (2003)

REQUESTS FOR RELIEF FROM CODE REQUIREMENTS PAGE 8 OF 9 NO. V-RR10 9002A Containment Spray Pump #I Discharge Check Valve 9002B Containment Spray Pump #2 Discharge Check Valve Catemor: C Code Class: 2 Test Rent: Part 10 does not provide for sampling.

Function:

These check valves function to allow full-flow during containment spray following a LOCA.

They close to prevent backflow of recirculating post-LOCA sump water back to the RWST in the event that valve 900 IA or 9001B is open.

Basis:

These check valves cannot be exercised during power operation because the system alignment for testing would require a containment entry to manually isolate the spray headers for testing and require placing the RHR system in an unanalyzed condition.

It is impractical to test these valves during shutdowns as the flowpath through these valves disables a train of the RHR system. The shutdown test alignment for partial or full stroking the valves places the RHR system in a degraded and precarious operating configuration, and creates the potential for inadvertent spraying of containment, inadequate RHR flow to the RCS, or overfilling of the reactor vessel or refueling cavity. The t valves are located in essentially dry pipe and are not subject to cycling; therefore, potential degradation mechanisms are minimal.

These valves are not equipped with mechanical exercisers, position indicators or differential pressure instrumentation.

These valves will be non-intrusively tested (NIT) on a sampling program, per NUREG-1482. This program will NIT one valve each refueling outage, on a rotating schedule, while full flow testing the other valve.

If any degradation is detected that interferes with the valve's operability, then the valve will be disassembled, internally inspected, and manually full stroke exercised during the same outage. In addition, the other valve in this group will be NIT during the same outage.

Justification:

Preapproved per NUREG-1 4S2, section 4.1.2.

I I

I I

i I

I 10006620.1ST 40MIS 130 I

• 8.

PACIFIC GAS & ELECTRIC COMPANY DIABLO CANYON POWER PLANT - UNITS I & 2 INSERVICE TESTING PROGRAM PLAN - PUMPS AND VALVES TABLE 2.3

• ASME/ANSI OM-1987 (INCLUDING OMa-1988 ADDENDA) REV 20 (2003)

REQUESTS FOR RELIEF FROM CODE REQUIREMENTS PAGE 9 OF 9 NO. V-RR11 Valves: MS-5166, SG-2 Steam to Auxiliary Feedwater Pump #I Check Valve MS-5 167, SG-3 Steam to Auxiliary Feedwater Pump #1 Check Valve Category: C Code Class: 2 Test Reit: Part 10 does not provide for sampling.

Function:

These check valves function to supply steam to the turbine driven auxiliary feedwater pump. The valves also have a safety function in the closed (reverse-flow) position to prevent an intact steam generator from blowing down to containment through the turbine driven AFW pump steam supply line following a MSLB.

Basis:

Full stroke opening is verified on a cold shutdown basis, but valve reclosure capability cannot be verified.

These valves are not equipped with mechanical exercisers, position indicators or differential pressure instrumentation. There are no test connections or taps installed that would allow reverc-flow seating verification for these check valves. Alternatively, the ability of the valve to close following actuation will be verified by disassembly and internal inspection on a rotational basis, one valve each refueling outage. If any degradation is detected that interferes with the valve's operability, then the opposite train valve will also be disassembled and internally inspected during the same outage. The valves will be part stroke tested after r%.eassembly.

Justification:

Disassembly and inspection each refueling outage is per.Part 10, paragraph 4.3.2.4(c).

Disassembly and inspection sampling program is preaporoved per NRC Generic Letter 89-04, Attachment I, position 2.

10006620.1ST 40MIS 131